Office of Compensation Analysis and Support 

(OCAS) 

Document No. OCAS-IG-001 

Effective Date: 11/21/2007 

Revision No. 3 

EXTERNAL DOSE RECONSTRUCTION IMPLEMENTATION 

GUIDELINE 

Page 1 of 77 

Approval: 

J. W. Neton, Associate Director for Sci

___Signature on file__________ Date: _11/21/2007___ ence 

Concurrence: L. J. Elliott, Director _ Signature on file _ Date: 11/21/2007 

 

 

 

_ 

____ _ __ 

Supersedes: 

Rev 2 

TABLE OF CONTENTS 

Section Title Page 

TABLE OF CONTENTS .......................................................................................1 

1.0 INTRODUCTION ............................................................................................5 

1.1 Dose Reconstruction Requirement............................................................................ 5 

1.1.1 Adequately Monitored ........................................................................................... 5 

1.1.2 Not Monitored........................................................................................................ 5 

1.1.3 Monitored Inadequately......................................................................................... 5 

1.1.4 Monitoring records incomplete or missing............................................................ 6 

1.2 External Radiation Exposures................................................................................... 6 

1.2.1 Photon exposures ................................................................................................... 6 

1.2.2 Neutron Exposures................................................................................................. 8 

1.2.3 Electron (Beta Particle) Exposures ........................................................................ 8 

1.3 Dose Reconstruction - Hierarchy of Data................................................................. 9 

1.4 Initial Dose Assessment ............................................................................................ 10 

1.4.1 Estimated Low Dose............................................................................................ 10 

1.4.2 Estimated High Dose ........................................................................................... 10 

1.5 Conversion to Organ Dose ....................................................................................... 11 

1.6 Uncertainty ................................................................................................................ 11 
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2.0 EXTERNAL DOSE RECONSTRUCTION – MONITORING DATA...............12 

2.1 Photon Dose ............................................................................................................... 12 

2.1.1 Dosimeter Dose.................................................................................................... 12 

2.1.2 Missed Dose......................................................................................................... 16 

2.1.3 Occupational Medical Dose................................................................................. 17 

2.1.4 Environmental Dose............................................................................................. 18 

2.2 Neutron Dose ............................................................................................................. 19 

2.2.1 Dosimeter Dose.................................................................................................... 19 

2.2.2 Missed Dose......................................................................................................... 22 

2.3 Electron Exposures ................................................................................................... 22 

2.3.1 Dosimeter Dose.................................................................................................... 23 

2.3.2 Missed Dose......................................................................................................... 23 

2.3.3 Skin Contamination ............................................................................................. 24 

3.0 EXTERNAL DOSE RECONSTRUCTION – INCOMPLETE, MISSING OR NO 

MONITORING DATA..........................................................................................24 

3.0.1 Interpolation of Missing Personal Monitoring Data ............................................ 25 

3.0.2 Extrapolation from Incomplete Personal Monitoring Data ................................. 25 

3.0.3 No Personal Monitoring Data .............................................................................. 25 

3.1 Photon Exposures...................................................................................................... 25 

3.1.1 Photon Dose Reconstruction – Co-worker Data.................................................. 25 

3.1.2 Photon Dose Reconstruction – Survey Data........................................................ 26 

3.1.3 Photon Dose Reconstruction – Source Term....................................................... 27 

3.1.4 Photon Dose Reconstruction – Control Limits .................................................... 28 

3.2 Neutron Exposures.................................................................................................... 29 

3.2.1 Neutron Dose Reconstruction - Co-worker Data................................................. 29 

3.2.2 Neutron Dose Reconstruction – Survey Data ...................................................... 29 

3.2.3 Neutron Dose Reconstruction - Source Term Data ............................................. 30 

3.3 Electron Exposures ................................................................................................... 31 

3.3.1 Electron Dose Reconstruction - Co-worker Data ................................................ 31 

3.3.2 Electron Dose Reconstruction - Survey Data ...................................................... 31 

3.3.3 Electron Dose Reconstruction - Source Term ..................................................... 32 

4.0 CONVERSION TO ORGAN DOSE ..............................................................33 

4.1 Photon Dose ............................................................................................................... 33 

4.1.1 Development of the Monitored Exposure/Dose to Organ dose factor................ 34 

4.1.2 Area survey or source term data to Organ Dose .................................................. 35 

4.1.3 Dose Conversion Factor Simplification............................................................... 35 
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4.2 Neutron Dose Conversion......................................................................................... 36 

4.2.1 Area Monitoring Data to Organ Dose.................................................................. 36 

4.2.2 Personal Monitoring Data to Organ Dose............................................................ 37 

4.3 Electron Dose Conversion Factors .......................................................................... 38 

4.4 Exposure Energy and Geometry ............................................................................. 38 

4.4.1 Dosimeter and Missed Dose Geometry ............................................................... 39 

4.4.2 Occupational Medical Exposure Geometry......................................................... 40 

4.4.3 Environmental Exposure Geometry..................................................................... 40 

4.5 Dose Conversion Uncertainty .................................................................................. 40 

4.5.1 Energy Uncertainty .............................................................................................. 40 

4.5.2 Geometry Uncertainty.......................................................................................... 40 

5.0 ANNUAL ORGAN DOSE & DISTRIBUTION ...............................................41 

5.1 Organ Dose Computation......................................................................................... 41 

5.1.1 Organ Dose Estimate ........................................................................................... 41 

5.1.2 Uncertainty Distribution ...................................................................................... 41 

5.2 Dose Distribution Determination/Categorization .................................................. 42 

5.3 IREP-Excel Reporting Format ................................................................................ 42 

6.0 REFERENCES .............................................................................................43 

APPENDIX A – PHOTON DOSE CONVERSION FACTORS (DCF)..................46 

APPENDIX A – NEUTRON DOSE CONVERSION FACTORS (DCF) ...............63 

APPENDIX B - IREP-EXCEL INPUT FORMAT .................................................77 
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Record of Issue/Revisions 

Issue 

Authorization 

Date 

Effective Date Revision 

No. Description 

May 2002 May 2002 0 External Dose Reconstruction 

Implementation Guideline 

August 2002 August 2002 1 

Updated Photon Dose Conversion Factors 

(Appendix B) to be consistent with IREP 

version 5.2. The intermediate energy 

photons cutoff changed from 200 keV to 

250 keV. 

Updated Occupational Medical Dose 

section (2.1.3) to include calculation of 

dose from x-ray machine parameters. 

8/25/2006 8/25/2006 2 Major Revision. Includes several changes 

including but not limited to: 

- Correction factors for ROT and ISO 

DCF values for Bone (RM and Surf), 

Esophagus, and Lung 

- Clarification on the methodology for 

determination of missed dose. 

Provided policy on handling of 

recorded doses less than LOD. 

- Introduced the concept of using 

neutron/photon ratios to determine a 

neutron dose for some dose 

reconstructions. 

11/21/2007 11/21/2007 3 Section 2.2.2.2.1 was modified to clarify 

the evaluation of missed neutron data 
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November 21, 2007 3 OCAS-IG-001 

1.0 INTRODUCTION 

The purpose of this document is to provide guidance on the components, standards, and 

methods of external radiation dose reconstruction for probability of causation calculations 

in support of the Energy Employees Occupational Illness Compensation Program Act 

(EEOICPA). It is to be used as a source to help provide specific guidance and methods 

which can be found in site profiles and other site-specific documents. External radiation 

dose results from exposure to a radiation source that is outside of the body. The photon 

or particle radiations travel through the air and are absorbed in a tissue of the body. 

1.1 Dose Reconstruction Requirement 

The first step in the photon dose reconstruction is to determine whether there was any 

potential for external radiation exposure at the facility. At most Department of Energy 

(DOE) facilities and Atomic Weapons Employers (AWE) there is a potential for radiation 

exposure. When no radioactive material was processed or stored, an external dose 

reconstruction is not necessary. The three groups of workers who require dose 

reconstruction are: 1) workers who were not monitored for radiation exposure; 2) workers 

who were monitored inadequately for radiation exposure; and, 3) workers whose 

monitoring records are incomplete or missing (42CFR82.3(a) 2002). 

1.1.1 Adequately Monitored 

In general, external monitoring data collected since the implementation of 10 CFR Part 

835 could be considered adequately monitored. When a claimant has been monitored 

adequately using either film badge dosimetry or thermoluminescent dosimetry (TLD) in 

accordance with the Department of Energy Laboratory Accreditation Program 

(DOELAP), these data shall be used to compute the annual dose for the claimant. The 

associated uncertainty should be assumed to be normally distributed and should be 

obtained from the site dosimetry office. 

1.1.2 Not Monitored 

Many of the Atomic Weapons Employer (AWE) workers were not individually 

monitored for radiation exposure. At some facilities, radiation surveys were conducted 

and this data, in conjunction with frequency of exposure, should be used to estimate the 

annual dose. When no radiation monitoring data is available for a facility, scientifically 

reasonable estimates of exposure should be developed based on the source term or 

quantity of radioactive material handled at the facility. 

1.1.3 Monitored Inadequately 

At some facilities, only a small sample of the work force was monitored to ensure 

compliance with radiation exposure limits. As an example, although construction 

workers were often not monitored, it may be possible in some instances to use workers 

who received similar exposures, such as radiological control technicians who monitored 

the work activities, to estimate external dose. For workers at these sites, the highest 

recorded value for similar work group should be assigned to the unmonitored worker. 
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November 21, 2007 3 OCAS-IG-001 

In addition to incomplete monitoring practices, most early workers at DOE facilities were 

monitored inadequately compared to modern standards. In most instances, the missed 

dose alone can exceed 500 mrem/year. At many facilities, routine monitoring for neutron 

exposures was not initiated until the late 1950s. In general, monitoring data prior to 1960 

must be evaluated cautiously due to technological shortcomings and because monitoring 

programs were designed to ensure compliance with a 12 rem/year exposure limit 

compared to the 5 rem/year current standard. For these workers and others with 

uncertain dose information, an evaluation of their dosimetry (or monitoring) data in 

combination with estimates for missed dose, occupational medical exposures, and 

environmental on-site dose should be used to determine the total annual external dose. 

1.1.4 Monitoring records incomplete or missing 

When monitoring records are incomplete or missing, the monitoring data prior to and 

after the missing data can be used to interpolate the missing data. When only post 

monitoring data is available, extrapolation should be used with caution, accounting for 

engineering administrative changes that might have been instituted which reduced 

exposures. In addition, co-worker data can be used to fill in missing or incomplete 

records. 

1.2 External Radiation Exposures 

The absorbed dose is to be calculated for the organ where the primary cancer exists. 

Interactive RadioEpidemiological Program (IREP) is used to calculate the probability of 

causation for an individual worker. For external radiation, there are three types of 

exposure; photon, neutron, and electron. Photon exposures are divided into three energy 

categories (< 30 keV, 30-250 keV, and >250 keV). Neutrons are divided into 5 energy 

categories (< 10 keV, 10-100 keV, 100-2000 keV, 2-20 MeV, and >20 MeV). While 

there are two electron categories in IREP, only the > 15 keV is considered to be a source 

of external radiation. Electrons below 15 keV do not have sufficient energy to penetrate 

the epidermal layer of the skin and, therefore, are not considered an external radiation 

hazard. Typically, external electrons are primarily of interest in skin cancer claims, 

however, depending on the beta particle energy, the dose can be significant for the 

development of breast and testicular cancer as well. 

1.2.1 Photon exposures 

The four basic components of photon exposures are the individual’s radiation monitoring 

data from dosimeters (DD), the unrecorded or unmeasured dose commonly referred to as 

the missed dose (DM), the occupational medical dose from medical monitoring x-rays 

(DOM), and the environment dose primarily from stack emissions (DEN). The sum of 

these doses in each calendar year comprises a worker’s annual occupational photon dose 

(Dγ). 

Dγ = DD + DM + DOM + DEN 
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November 21, 2007 3 OCAS-IG-001 

1.2.1.1 Dosimeter Dose (DD) 

Most radiation workers have been routinely monitored for exposure to radiation to ensure 

compliance with health and safety standards. External radiation monitoring was typically 

conducted on an individual basis using pocket ionization chambers, film badges, and 

thermoluminescent dosimeters. 

1.2.1.2 Missed Dose (DM) 

Missed Dose is the unrecorded or unmeasured external photon dose that is a result of 

relatively high detection limits in early years of radiation monitoring combined with 

short-monitoring durations or a high dosimeter exchange frequency. In some instances, 

the missed dose is not the result of a technological limitation, but results from a recording 

practice, which considered some doses de minimus, which resulted in positive readings 

below some threshold being recorded as zero. Missed dose is particularly problematic in 

early years of radiation monitoring. During this time interval, missed dose was 

considered relatively unimportant since the annual occupational limits for radiation 

exposure were quite high (12 rem/year). As annual exposure limits were reduced, and 

monitoring technology improved, the magnitude of the missed dose has significantly 

decreased such that when quarterly TLD monitoring was implemented, the missed dose is 

generally less than 40 mrem/year. 

1.2.1.3 Occupational Medical Dose (DOM) 

In early years, the latent effects of radiation exposure were not well understood, and 

short-term tolerance dose limits were believed to be protective. With improved 

technology came new screening techniques such as photofluorography. Medical 

personnel used these new techniques to screen and diagnose patients for diseases such as 

tuberculosis. In addition, these screening techniques were used to monitor for excess 

exposure to heavy metals such as uranium. According to Parker (1947), the entrance dose 

in photofluorography was about 1 R. Cardarelli et al (2001) noted that the bone marrow 

dose from photofluorography (≈ 800 mrad) was nearly two orders of magnitude greater 

than that of conventional diagnostic x-rays (≈ 10 mrad). At some facilities, 

photofluorography or other screening x-rays were required as part of the routine medical 

monitoring program. Since these examinations were required for employment, they are 

considered part of the occupational radiation exposure under EEOICPA. Primarily these 

exposures will be in either the < 30 keV or the 30-250 keV energy group. It should be 

noted that only medical exposures that were required as a condition of employment are 

included in the occupational medical dose. Diagnostic and therapeutic procedures not 

required for employment are not included. 

1.2.1.4 Environmental Dose (DEN) 

Typically, energy employees who were not categorized as radiation workers were not 

monitored using personal dosimeters, however, the work environment for these 

employees was often routinely monitored using area dosimeters or periodically monitored 

using survey instrumentation to measure the “background” environmental radiation 

levels. At many of these facilities, routine monitoring stations have recorded the average 

photon dose in a general area or at the plant boundaries. At several DOE facilities, 
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ber 21, 2007 3 OCAS-IG-001 

1.2.2.1 Neutron Dosimeters (DD) 

1.2.2.2 Neutron Missed Dose (DM) 

Effectiv

Novem

radioactive emissions from plant stacks have been known to significantly increase the 

“background” radiation levels on the plant site. In general, the dose from increased 

background is rather low. 

The environmental dose at each facility should be evaluated. For example, during some 

operations such as the “green” runs at Hanford and INEEL, the release of fission products 

to the atmosphere significantly increased the ambient radiation levels well above natural 

background. At Hanford for instance, the environmental dose in May 1947 was reported 

as 21.7 mrep/month and 68.2 mrep/month for the 200-W and 200-E area respectively. 

The monthly environment gamma dose at the 100-B area was 12.4 mrep/month, which is 

near natural background levels. With prevailing winds from the west to east, clearly the 

downwind areas had significantly elevated radiation exposures. Since most routine 

emissions and even many of the non-routine emissions would not result in exposures 

exceeding the annual occupational limits, some workers at the facility, including security 

and construction workers, were not monitored for this exposure. 

1.2.2 Neutron Exposures 

The two basic components of the neutron dose are the individual’s monitored dose from 

dosimeters (DD) and the unrecorded or unmeasured dose commonly referred to as the 

missed dose (DM). Since neutron exposures from man-made sources do not exist in the 

environment, nor are neutrons used in diagnostic or medical procedures, the later two 

categories are not included in the external radiation dose reconstruction. 

D N D M = D + D

Since the beginning of nuclear operations, neutrons have been monitored in the work 

place through radiation surveys, typically using either moderated boron tri-fluoride (BF3) 

detectors or tissue equivalent proportional counters. Individual neutron exposures have 

typically been measured and recorded using specially designed pocket ionization 

chambers, nuclear track emulsion type A (NTA) film, and thermoluminescent dosimeters 

(TLD). 

Neutron monitoring was not fully implemented at some sites until the late 1950s. Early 

use of NTA film resulted in relatively large missed doses for neutron exposure. For 

example, at Hanford, neutron film was read on a weekly basis with a stated limit of 

detection (LOD) of 90 mrem. At some sites, due to the difficulty in reading the film, 

many monitored workers’ films were not read unless the photon dosimeter exceeded a 

certain threshold. This administrative practice has also resulted in some significant 

missed dose. This dose must be evaluated and added to the overall neutron dose. 

1.2.3 Electron (Beta Particle) Exposures 

Generally, external electron exposures are only important for surface tissue such as skin. 

Thus, for skin cancer, a dose reconstruction from exposure to electrons is required. The 
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November 21, 2007 3 OCAS-IG-001 

exposure to skin can originate from either a strong unshielded electron source such as Sr90/Y-90 or uranium daughters, or from skin contamination with beta/gamma emitters. 

The other two organs for which external electron exposure from high energy electrons (> 

1 MeV) might be significant are the testes and the breast. For breast and testicular 

cancer, an evaluation of the maximum electron energy exposure should be conducted. 

Generally, if the electron energy is less than 1 MeV, the dose conversion factor (DCF) 

will be zero since the electron does not have sufficient energy to penetrate the outer layer 

of skin (ICRP 74, 1996.) In these cases a dose reconstruction is not necessary. As with 

neutron doses, there are typically only two components of the electron dose, dosimeter 

dose and missed dose. Electrons have not typically been used for diagnostic occupational 

medical monitoring. An electron environmental dose is also usually not applicable since 

immersion in a cloud would generally have been monitored. While occupational medical 

and environmental doses are not included in electron dose reconstruction, skin 

contamination from beta-gamma emitters poses a unique exposure scenario that should 

be included in skin cancer cases. The general form of the electron dose equation is as 

follows: 

D E D M S = D + D + D

1.2.3.1 Dosimeter Dose (DD) 

In early years, beta exposures were monitored using an open window of a film dosimeter. 

In the mid 1970s TLDs replaced the film badges at most facilities. One major advantage 

of the TLD is that the detector is similar to tissue and a shallow dose could be measured 

more accurately. 

1.2.3.2 Missed Dose (DM) 

As with most dosimeters, there was a limit of detection that has resulted in some missed 

dose. In addition to readings below a limit of detection, many early monitoring programs 

measured but did not record the open window dose in the official dose of record for the 

individual. 

1.2.3.3 Skin Contamination (DS) 

While skin contamination can result in some deep dose from photons, the shallow dose 

from the electrons is usually several orders of magnitude greater and should be included 

in dose reconstruction for skin cancer. Data such as isotope, and quantity of activity from 

skin contamination incidents have typically been reported in a claimant’s radiological 

file. 

1.3 Dose Reconstruction - Hierarchy of Data 

Generally, individual dosimeter data should be used whenever possible and given 

precedence over personal monitors, survey data or source term data. In some instances, 

dosimeters were not worn or, in the case of neutrons, the NTA film limit of detection 

(LOD) was relatively high compared to the pocket ionization chamber. In these 

circumstances, the personal monitor can be used, however caution should be employed to 

ensure the dose is not a false positive or the sum of the personal monitors exceeds the 
 

Hierarchy Data Source Examples 

1 Personal Dosimeter Film Badge, TLD 

2 Personal Monitors Pocket Ionization Chambers 

3 Co-Worker Data Film Badge, TLD, Pocket Ionization 

Chambers, etc. 

4 Area Monitoring Work Place Radiation Surveys, Ambient 

Air room monitors, duration of exposure 

5 Source Term Source strength, distance from source, 

duration of exposure, and shielding 

information 

6 Radiation Control Limits Generally, workplace posting has been 

required when the dose rate exceeded 0.025 

mSv/hr. 

 

 

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November 21, 2007 3 OCAS-IG-001 

LOD of the personal dosimeter. Table 1.1 outlines the general hierarchy of data sources 

that should be employed for dose reconstruction under EEOICPA. 

Table 1.1 Hierarchy of Data Sources for Dose Reconstruction 

1.4 Initial Dose Assessment 

In order to achieve the greatest efficiency in conducting external dose reconstruction, a 

health physicist should review the case to arrive at a rough estimate of exposure to 

determine if the case falls into either a very low or very high potential exposure category. 

External cumulative doses across numerous facilities have been observed to follow a log 

normal distribution with some very high exposures and some very low exposures. In 

some instances, particularly with short exposure durations, reasonable and conservative 

upper dose estimates can be developed based on relatively little data. Likewise, based on 

an initial review of exposure records, a health physicist should be able to identify workers 

with likely high doses and may only need to conduct a partial dose assessment to 

definitively place a worker’s exposure into a high exposure. An initial dose assessment 

can greatly facilitate the throughput of dose reconstructions by conservatively 

overestimating a low dose exposure that would likely not result in a high probability of 

causation and underestimating a high dose exposure that would result in a high 

probability of causation. 

1.4.1 Estimated Low Dose 

This approach is most appropriate for short duration non-radiological workers who might 

have been exposed to low levels of environmental radiation. For example, an 

unmonitored clerical worker at a facility once walked through a radiological control area 

to deliver a message. The duration in the area was less than one hour and the maximum 

allowable dose rate in the area was 2.5 mrem/hr. Instead of using co-worker data, or 

actual survey data, the worker’s dose can be estimated to be a maximum of 2.5 mrem. 

1.4.2 Estimated High Dose 

Some workers have exceeded occupational limits through radiological accidents or 

incidents. In order to expedite their claims, a partial dose reconstruction should be 

conducted, provided, the outcome results in a high probability of causation. In cases 
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November 21, 2007 3 OCAS-IG-001 

where the probability of causation is not high, a more detailed dose reconstruction must 

be conducted. 

1.5 Conversion to Organ Dose 

For external dose reconstruction under EEOICPA, the organ or tissue which developed 

the cancer is the organ of interest. Implementing procedures will allow the dose 

reconstructor to identify the corresponding organ for which the external dose should be 

calculated using the ICD code. 

Typically, film badge and TLDs were worn on the upper front torso of the body. 

Depending on the monitoring era, these devices were calibrated to measure either 1) 

exposure, 2) the ambient dose equivalent, or 3) the penetrating dose at 10 mm using a 

standard phantom. The 10 mm penetrating dose is commonly referred to as the Hp(10). 

For film badge dosimetry calibrated to exposure in roentgens (R), the conversion to 

ambient dose equivalent (H*

(10)) can be found in ICRU 43 (1988). 

In turn, the ambient dose equivalent (H*(10)) can be converted to air KERMA (Ka) using 

data from ICRP 74 (1996). The personal dose equivalent (Hp(10)) can also be converted 

to air KERMA using data from ICRP 74 (1996). Once the monitoring data has been 

converted to air KERMA, the organ dose can be calculated based upon the most likely 

exposure geometry for each of the IREP radiation types and associated energy intervals. 

The methodology describing these conversions is further discussed in section 4. 

While these calculations are straightforward, the conversion of early film badge data to 

exposure energy is not. Unless corrections were made, the calibration of the early film 

badges using a radium or Cs-137 (high energy) gamma source resulted in an 

overestimation of the low energy exposure received by a worker. Thus, when 

appropriate, low energy exposures should be corrected for this overestimation. 

1.6 Uncertainty 

The general approach to uncertainty in external dose reconstruction is to treat each 

variable as a distribution and then employ Monte Carlo sampling of each of the 

distributions to determine the overall uncertainty of the annual dose estimate. In general, 

the uncertainty in the measured dosimeter dose and the occupational medical dose is 

assumed to follow a normal distribution, while the uncertainty in the missed dose and the 

environmental dose is assumed to follow a log normal distribution. The uncertainty in 

the conversion of exposure or personal dose equivalent to organ dose is assumed to 

follow a triangular distribution with the upper and lower bounds determined by the most 

and least favorable geometry and energy. 
 

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November 21, 2007 3 OCAS-IG-001 

2.0 EXTERNAL DOSE RECONSTRUCTION – MONITORING DATA 

When monitoring data are available, the three types of exposure are the photon dose, 

neutron dose, and electron exposures. As previously discussed, electron exposures are 

usually relevant for skin cancer but for high-energy electron exposure, testicular and 

breast doses should be evaluated. 

2.1 Photon Dose 

As discussed in the introduction, the four components of photon dose are the dosimeter 

dose (DD), the missed dose (DM), the occupational medical dose (DOM), and 

environmental dose (DEN). The sum of these doses in each calendar year comprises a 

worker’s annual occupational photon dose (Dγ). 

2.1.1 Dosimeter Dose 

2.1.1.1 Background 

Since the beginning of nuclear weapons research and production, individual workers have 

been monitored using personal dosimeters at many facilities. Initial monitoring was 

conducted using film badges with various exchange frequencies. By the late 1970s most 

monitoring programs transitioned to TLDs. Through the years, technological 

developments have greatly improved the accuracy and sensitivity of the dosimeters. 

2.1.1.2 Method 

In general, the dosimeter dose is a summation of the individual dosimeter readings. As 

listed in Table 1.1, the following hierarchy should be used to determine an individual’s 

dosimeter dose: personal dosimeter (film badge or TLD), pocket ionization chamber, 

group or co-worker dosimeter(s). Within the NIOSH-IREP probability of causation 

program, there are three photon energy bands; 1) below 30 keV, 2) 30 to 250 keV, and 3) 

above 250 keV. Therefore, some separation of the dose from each energy band is 

required. 

At most of the larger facilities, multi-shielded film badges or multi-element TLDs have 

been used since the mid 1960s. Since only three energy bands are used in the probability 

of causation calculations, the differences between various filter doses can provide insight 

into the gross energy distribution at the facility. To the extent possible, these differences 

should be used to estimate the relative energy distributions in earlier years when only two 

element film badges were used. If individual energy distribution information is not 

available for two element film badges, the open window dose should be used as a 

claimant friendly estimate of the 30 to 250 keV dose. It is recognized that early film 

badges over-responded to low-energy photons, however corrections for this overresponse are only recommended when scientific studies have been conducted and the 

exposure geometry and energy distribution are well known. 

When monitoring data do not indicate the relative energy distribution, the distribution can 

be estimated based upon either the site radionuclide inventory or the relative energy 
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November 21, 2007 3 OCAS-IG-001 

distribution which can be estimated for most facilities based upon a review of historical 

operations. 

For modern radiological monitoring programs, especially DOELAP accredited 

laboratories, the energy distribution should be well characterized for the processing of the 

TLDs and this information should be readily available from the site dosimetry program. 

2.1.1.3 Uncertainty 

The general approach that follows may be used with site specific data, which has been 

collected for Technical Basis Document development, in order to develop the dosimetric 

uncertainty for that site. 

2.1.1.3.1 Film Badge Uncertainty 

A technical committee appointed by the National Academy of Sciences outlined three 

components (laboratory, radiological, and environmental) of uncertainty in personal 

dosimetry for film badge dosimetry used during atmospheric nuclear tests (NRC 1989). 

The uncertainty in the environmental component is discussed in section 2.1.3, and the 

radiological component is discussed in the exposure geometry section 4.4. Thus the 

laboratory uncertainty is the only source of uncertainty addressed in this section. 

The uncertainty for film badge measurements is a function of the film type or packet used 

at the facility. The laboratory film badge uncertainty is relatively dependent on the 

exposure. Brodsky et al. (1965) extensively studied the accuracy of film badge 

dosimeters and concluded that under good laboratory conditions, the uncertainty can be 

as low as 10% to 15%, even at low doses. However, at many facilities, the uncertainty 

was much greater at low doses. Fundamentally, the absolute uncertainty at the 95% 

confidence should not be less than the limit of detection (LOD). For simplicity, the 

approach outlined by the National Research Council (1989) will be employed for dose 

reconstruction under EEOICPA. However, the additional uncertainty discussed for 

exposures below 200 mR will not be employed, since routine monitoring is generally 

more precise than large sampling events such as atmospheric test monitoring (See Figure 

2.1). This approach, in combination with available facility dosimetry data, may be 

adapted for use in the individual site profile development. The uncertainty associated 

with each dosimeter reading is assumed to be normally distributed, where the dosimeter 

reading is the mean and the upper 95% confidence dose is calculated by multiplying the 

uncertainty factor K(E) by each dosimeter reading using the following equations: 

⎡σ (E)⎤ K(E) =1+1.96⎢

⎣ E ⎥⎦

σ * 

σ (E) = eγE 

D∞γ

where: 

E = Exposure in roentgen 

σ* = Densitometer reading uncertainty typically 0.015 density units 
 

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November 21, 2007 3 OCAS-IG-001 

D∞ = Saturation Density of the Film (Dupont 502 = 2.8) 

γ = film sensitivity (Dupont 502 ≈ 0.25) 

2.1.1.3.2 TLD Uncertainty 

The uncertainty of thermoluminescent dosimeters is generally lower than film badge 

dosimeters, however the uncertainty is still somewhat dependent on the dose. Several 

biases can occur that, when combined, contribute to the random error. The fading of the 

dosimeter, especially in high temperature environments, results in a slight decrease in the 

measured dose. Conversely, the annealing process can result in residual artificial dose 

and spurious luminescence from contaminants, thereby overestimating the true dose. A 

simple estimate of uncertainty based on Hirning (1992) is to divide exposure into two 

components with one part based on the limit of detection, which dominates in the low 

dose region, and the other based on a best estimate of overall dosimeter uncertainty 

(generally 5 - 10%). A key assumption is that the two components are uncorrelated. This 

is appropriate since the variance in the low dose region would be dominated by 

measurement or counting statistics (i.e. total counts above background on a photo 

multiplier tube (PMT)). Conversely, in the upper dose region, the variance from counting 

statistics plays a rather insignificant role, however the uncertainty associated with the 

calibration, energy response of the dosimeter, and fading begin to dominate. Generally 

the relative uncertainty associated with radiation monitoring has been less than 5 - 10% at 

relatively high dose levels. This uncertainty increases with decreasing dose from 10 -

15% in the hundreds of millirem (Hendee 1967; Wallace, Watkins 1968) to 

approximately 100% at the LOD. 

2.1.1.3.3 Simplified Dosimetry Uncertainty 

In the development of the site-specific Technical Basis Document, exposure data may be 

used to estimate the dosimetric uncertainty using the following simplified uncertainty 

method based on Hirning (1992). 

The minimum detection level (MDL), sometimes called the critical limit (LC), is generally 

defined as the point when the uncertainty of the reading at the 95% confidence level is ±

100%. The standard deviation at this level can be defined as: 

L L

σ MDL = C C = k 1.96 

Assuming that σMDL ≈ σn (the standard deviation of the null readings) and that the 

standard deviation at the high dose level (σμ) is a constant relative percentage on the 

order of 10-20%, a simple estimate of uncertainty based on exposure level can be defined 

as: 

2 * ⎛ L ⎞

2 ⎛ σ ⎞ C σ (E) = ⎜ ⎟ + ⎜ (E)⎟ ⎜ ⎟ ⎝ ⎠ 1.96 100 ⎝ ⎠

where: 
 

 

 

 

 

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LC = Critical Limit 

* σ = Estimated percent standard error 

E = Exposure or Dose 

Figure 2.1 demonstrates reasonable agreement between the 95% Uncertainty Factors, 

K(E) using the film badge methodology and the simplified method over a range of 

exposures. The simplified method was calculated using a 30 mrem detection threshold 

and a standard error of 10%. 

0.0 

0.5 

1.0 

1.5 

2.0 

2.5 

3.0 

3.5 

4.0 

4.5 

95% Uncertainty Factor K(E)

Film Badge Uncertainty Method 

Simplified Uncertainty 

0.010 0.100 1.000 

Dose (rem ) 

Figure 2.1 Comparison of film badge uncertainty to simplified uncertainty 

2.1.1.3.4 Uncertainty Combination 

The uncertainty from each film dosimeter should be calculated and the combined annual 

uncertainty should calculated using standard error propagation methodology (square root 

of the sum of the squares) as shown in the following equation. 

2 2 2 2 2 σ D =σ 1 2 3 + σ + σ + ...σ i 

where 

σ D = Uncertainty of Annual dose

σ = Uncertainty of a Single Dosimeter i 
 

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2.1.2 Missed Dose 

2.1.2.1 Background 

In the scientific literature there are several different models that can be used to assess the 

missed dose (Strom 1988, Hornung and Reed 1990, Finklestein and Verma 2001). 

Recently, Taulbee, et al (2001) evaluated several models and concluded that the LOD/2 

method resulted in a slightly positive bias (overestimate) of the true dose. While other 

missed dose methods might be more accurate on a large scale, for claimant friendly dose 

reconstruction, a bias which slightly overestimates the missed dose is acceptable. 

2.1.2.2 Method 

The National Research Council, in their evaluation of film badge dosimetry for 

compensation of atomic veterans, recommended the use of the Limit of Detection LOD/2 

method. This scheme has been used in other compensation programs and has been 

shown to result in a slight positive bias. The method to be used for dose reconstruction 

related to EEOICPA is to assign a dose equal to the LOD divided by 2 for each dosimetry 

measurement (film badge, pocket ionization chamber or TLD) that is recorded as zero or 

if it is below the limit of detection divided by 2. Readings greater than or equal to LOD 

divided by 2 are to be used as recorded. See Table 2.1 as an example. 

Table 2.1 Example of assigned dose based on dosimetry records 

Site Recorded 

Value 

(mrem) 

Limit of 

Detection 

(mrem) 

LOD/2 

(mrem) 

Assigned Missed 

Dose (mrem) 

Assigned or 

Recorded Dosea 

(mrem) 

10 30 15 15 15 

25 30 15 25 

15 30 15 15 

0 30 15 15 15 

Note: This table is for illustrative purposes only and is not to be used for actual dose reconstructions. 

a. Used in analysis of missed or measured dose, respectively. 

2.1.2.3 Number of Zero Measurements is Unknown 

When the number of zero measurements cannot be determined, the missed dose becomes 

more complicated. When only the annual dose is known, the number of zero doses 

should be estimated based on the dose level and the monthly, quarterly, or annual limits 

for that year, and the number of possible zero monitoring intervals. This would be the 

situation, for example, if an individual received a cumulative dose of 2140 mrem in a 

given year, at a facility that had a monthly monitoring frequency and the maximum 

permissible exposure limit was 1000 mrem per month. The minimum number of months 

in which this dose could have been received is 3. Therefore, the maximum number of 

missed dose months would be 9, and the minimum would be 0 since the dose could have 

been received evenly throughout the year. The central estimated number of months 

would be the median or 5, however the upper bound would be 9. 
 

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2.1.2.4 Uncertainty 

The missed dose uncertainty will be combined with the measurement, energy and 

geometric uncertainties in a Monte Carlo sampling technique described in Section 1. 

Since the “true” missed dose is not known, there is some probability that the actual 

missed dose could be as great as the LOD times the number of zero measurements. 

Likewise, there is some probability that the “true” missed dose is actually zero. 

According to Strom (1988), and as verified by Taulbee et al (2001), the log normal 

distribution dominates in the low dose region. Therefore the log normal distribution 

should be used for the uncertainty distribution for missed dose 

2.1.2.5 Multiple dosimetry monitoring 

There are some individuals who, given their specific job function, might have worn 

multiple monitoring badges during a particular monitoring period. At some facilities 

these workers were classified as ROVER status. The central tendency of the missed dose 

for these individuals should be calculated using the same LOD/2 methodology, however, 

the number of zero measurements should be based on the number of routine monitoring 

intervals in a given year. 

2.1.3 Occupational Medical Dose 

2.1.3.1 Background 

At many DOE facilities, physical examinations were required as a condition of 

employment. Some of these examinations included the use of diagnostic x-ray 

examinations. Because these were required, they are considered occupational dose for 

purposes of this program. Generally, these x-ray examinations result in a very small dose 

near the detection limit of film badge dosimetry. However in early years (< 1960) some 

facilities utilized photofluorography equipment that could deliver substantial doses. As 

early as 1947, radiological control programs recognized that the use of photofluorography 

would not be appropriate for radiological workers, however some clinics continued to use 

the procedure (Parker, 1947). While the typical bone marrow dose from a standard chest 

x-ray is approximately 10 mrem, a standard photofluorography unit delivered a bone 

marrow dose of approximately 800 mrem (Cardarelli et al, 2001). 

2.1.3.2 Method 

The calculation of the Occupational Medical Dose is straightforward. The most difficult 

component is determining site specific x-ray machine parameters and screening 

protocols. Organ doses are calculated using site specific or published information and 

dose conversion factors from ICRP Publication 34. Organ doses are provided in the 

individual site Technical Basis Documents or Technical Information Bulletins. X-rays in 

the diagnostic energy range consist of low energy photons (<250 keV). . 
 

 

 

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2.1.3.3 Uncertainty 

The uncertainty distribution about each diagnostic procedure is assumed to follow a 

normal distribution with DOM being the mean dose. If known, the standard deviation of 

the procedure should be used. 

2.1.4 Environmental Dose 

2.1.4.1 Background 

Historically, radioactive stack emissions have substantially increased radiation levels 

around some facilities. Regulation of stack emissions has generally been designed to 

protect the general population or the environment with particular attention to dose rate 

levels near the site boundaries. Since the mid 1970s, stack emissions at most facilities 

have generally been low enough that these emissions have been negligible compared to 

occupational dose. However, early stack emissions were not negligible compared to 

modern occupational limits and therefore will be considered, where appropriate, as part 

of the worker’s exposure. Unlike the previous three modes of external exposure, which 

could be either chronic or acute, the environmental dose is always assumed to be chronic. 

2.1.4.2 Method 

At large DOE facilities, the stack releases were fairly well documented and ambient air 

dose rates were measured at monitoring stations throughout the facility. Since detailed 

employment history is generally available either through facility records or through the 

Computer Assisted Telephone Interview (CATI), this history can be used in conjunction 

with area measurements to estimate the dose contribution from plant emissions. 

Generally the dose will be very low (< 10 mrem/month), but during some time periods at 

certain facilities, the dose rate could be as high as a 100 mrem/month. A review of 

historical plant records should be conducted to make this dose determination on a caseby-case basis. Since energy distributions are not generally known from the dose rate 

measurements, the entire measurement is assumed to be in the 30-250 keV energy range. 

The general equation to calculate the dose from plant emissions is given as: 

DEN = nD&

mO f 

n = number of months exposed 

D&

m = average monthly dose rate for year of interest

O f = Occupancy Factor (% of time on plant site) 

2.1.4.3 Uncertainty 

Ideally, the annual uncertainty should be calculated based on the standard deviation of 

monthly average dose rates or the standard deviation of all of the measurements. 

However in most instances this data will be difficult to obtain, thus some approximation 

of the uncertainty would be more reasonable. Based on the occupancy factor alone, it is 

highly unlikely that an environmental dose would ever exceed 500 mrem in a year. Thus 
 

2.2 Neutron Dose 

 

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November 21, 2007 3 OCAS-IG-001 

this value can be used as a conservative (claimant friendly) upper bound (95%) with DEN 

being the geometric mean of a log normal distribution. 

For dose reconstruction under EEOICPA the dosimeter dose and the missed dose will be 

used to calculate an individual neutron dose. 

As with photon exposures, the NIOSH-IREP program uses energy intervals to calculate 

the probability of causation from neutron exposures (Table 2.2). Neutrons, unlike 

photons, are high linear energy transfer (LET) radiation. In accordance with 42 CFR 82 

(2002), ICRP 60 (1990) radiation weighting factors (wR) will be used for dose 

reconstruction and reporting of dose. 

Table 2.2: Neutron energy intervals and associated ICRP 60 weighting factor and some examples of 

exposures or facilities where the specific neutron energy might be encountered. 

Neutron Energy 

(MeV) 

ICRP 60 Radiation 

weighting factor, wR 

Typical Exposure Scenario 

< 0.01 5 

Low energy neutron exposures include thermal neutrons 

commonly found around nuclear reactors or moderated 

neutron sources. More prevalent around heavy water 

reactors. 

0.01 – 0.10 10 

Intermediate energy neutron exposures can also result 

from operation around nuclear reactors as high-energy 

neutrons are moderated to thermal energies. 

0.10 – 2.00 20 

Commonly called fission spectrum neutrons, this is the 

most typical energy range from operation of light water 

or graphite moderated reactors. 

2.0 – 20.0 10 

Reactions between alpha particles from materials such as 

plutonium or polonium and light materials such as 

beryllium can result in the production of neutrons. 

These reactions are commonly called (α,n) reactions. 

This neutron energy interval also includes 14 MeV 

neutrons from fusion reactions. 

> 20.0 5 Exposures to neutrons greater than 20 MeV can result 

from work around accelerators. 

2.2.1 Dosimeter Dose 

2.2.1.1 Background 

Prior to the early 1950s personal neutron monitoring was conducted using boron lined 

pocket ionization chambers at most facilities. In the early 1950s some facilities began 

using neutron track emulsion (NTA) film for measurements of fast neutrons, and in the 

1960s, cadmium plates were used to distinguish between fast and slow neutrons. By the 

mid 1970s most facilities switched to TLDs, however several continued using NTA film. 

The boron-lined pocket ionization chambers measured slow or thermal neutrons. Due to 

the large variability associated with the boron lined pocket ionization chambers, an 

absorbing material such as cadmium or gadolinium was placed in a film badge to 
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measure thermal neutrons. Thermal neutrons absorbed by the material emit low energy 

photons in a n,γ reaction. The additional darkening of the film from the low energy 

gamma rays of the n,γ reaction were then compared to the film behind a similar material 

with a low thermal neutron cross section. The difference was a relative measure of the 

thermal neutron exposure. 

NTA film was far superior to the boron-lined pocket ionization chambers, however they 

suffered from an inability to accurately measure neutrons below about 500 keV (Griffith 

et al 1979). A variety of energy thresholds for NTA film dosimeters are cited in the 

scientific literature. Site specific information may be used to determine actual threshold 

values. 

With the introduction of thermoluminescent albedo dosimetry in the 1970s, neutron 

measurements improved with lower detection limits, however the relative uncertainty at 

higher doses remained generally about the same. 

2.2.1.2 Method 

Dose from neutrons is the summation of each of the dosimeter readings for a given year. 

Review of site data is typically required to evaluate the neutron energy spectrum, the 

calibration and reported quantity, and the radiation quality factors used. 

2.2.1.2.1 Neutron Energy 

When no energy information can be found, the exposure scenarios discussed in Table 2.2 

can be used to estimate the predominant energy. 

2.2.1.2.2 Calibration and Reported Quantity 

At some facilities, the calibration sources of the neutron dosimeters were changed 

thereby changing the response of the dosimeter. A determination of whether or not the 

radiological records were updated to reflect the change should be performed. 

2.2.1.2.3 Quality Factor 

In order to interpret site reported doses, some site-specific analysis of the quality factors 

used is required. Generally, since the 1950s, a quality factor of 10 has been applied to 

fast neutron exposures, however this has varied from 5 to 20 across facilities and time 

frames. 

2.2.1.3 Uncertainty 

The uncertainty associated with neutron monitoring is assumed to follow a normal 

distribution like the photon dosimeter dose. Several authors have reported general 

uncertainty to be about 20% to 30% (Oshino 1973, McDonald and Hadley (1985)). 

Schimmerling and Sass (1968) reported the standard deviation of two groups of irradiated 

dosimeters analyzed by commercial vendors from 1964 to 1966. Group A was irradiated 

on the first day of the badge wear period or cycle while group B was irradiated on the last 

day of the wear period just prior to reading. The group A badges generally displayed a 

systematic under-response due to latent image fading, while the group B badges 

displayed an over-response resulting in an overestimation of the irradiated dose. Within 
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November 21, 2007 3 OCAS-IG-001 

both of these groups, the uncertainty associated with reading the badges was provided. 

The reading uncertainty has been converted to the K(E) parameter in Figure 2.5. 

McDonald and Hadley (1985) conducted one of the most comprehensive reviews of 

neutron dosimeter response uncertainty at 12 DOE sites. They evaluated the response of 

various neutron dosimeters which included the albedo TLDs and NTA film dosimeters. 

As noted previously, McDonald and Hadley (1985) reported the overall uncertainty was 

10% to 25%. However, near the detection limit the uncertainty approached or exceeded 

100%. Phase 1 of this study provided the most comprehensive review of routine 

monitoring at the DOE facilities. The relationship between uncertainty and dose is 

depicted in Figure 2.5, using the upper 95% dose limit methodology discussed in the 

photon section of this guide and the coefficient of variation data provided by McDonald 

and Hadley (1985). 

Fix et al (1996) analyzed NTA film calibration data, which included reader uncertainty 

for the Hanford site from 1950 to 1961. Although these calibration doses were greater 

than 100 mrem, and all sources of uncertainty are not included, it is apparent that the 

observations reported by McDonald and Hadley in the 1980s should be reasonable 

approximations of the uncertainty over the monitoring time period from 1950-1990s. 

Note that this uncertainty factor does not account for any systematic bias that should be 

corrected for on a site-by-site basis as appropriate. 

Figure 2.5 95% Uncertainty factor K(E) calculated from various data sets. 95% Uncertainty Factor - K(E) 

4.0 

3.5 

3.0 

2.5 

2.0 

1.5 

1.0 

0.5 

0.0 

McDonald and Hadley (1985) 

Schimmerling and Sass (1968) Group A 

Schimmerling and Sass (1968) Group B 

Watson (1951) 

Fix et al. (1996) 

10 100 1000 

Dose (mrem) 
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2.2.2 Missed Dose 

2.2.2.1 Background 

Neutron monitoring was not fully implemented, or was generally inadequate, until the 

late 1950s. As a result, missed neutron doses have the potential to contribute 

significantly to the annual occupational dose, especially in early years of the DOE 

weapons complex. 

2.2.2.2 Method 

2.2.2.2.1 Monitoring Data - Below Limit of Detection 

Generally, neutron missed dose will be evaluated using the same method discussed for 

photons. However, when the neutron missed dose central estimate (nLOD/2) exceeds 

75% of the photon dose (dosimeter dose + missed dose), the exposure should be 

evaluated to determine if it should be considered to be an unmonitored exposure. If so, 

some other dose reconstruction method may be used to estimate the neutron dose. These 

alternate methods include but are not limited to the use of a site or area specific neutron 

to photon dose ratio, or radiation survey data combined with stay times (frequency of 

exposure). 

2.2.2.2.2 Unmonitored Neutron Energy Interval 

A worker cannot have an exposure to fast neutrons without an exposure to intermediate 

(Group II) or thermal neutrons (Group I), since the human body acts as a moderator. 

However, a worker can be exposed to only low energy neutrons if a moderator shielded 

the neutron source. Generally, Group II neutrons have gone unmonitored and unreported 

unless they have been accounted for in site specific algorithms. When site/facility 

specific neutron spectrums are known, respective doses in each missing group can be 

determined using the ratio of the dose within each energy interval. When no specific 

neutron spectrum information is known and both the thermal and fast components have 

been reported, the Group II dose can be estimated by interpolating the neutron fluence 

between the opposing groups. The conversion from dose to fluence is necessary since the 

dose conversion factor is different for thermal and fast neutrons. Once the interpolated 

fluence is known, the midpoint of the energy interval can be used to estimate the dose. 

2.2.2.3 Uncertainty 

The uncertainty associated with missed neutron dose should be evaluated as described in 

section 2.1.2 using the lognormal distribution. 

2.3 Electron Exposures 

Low energy electron exposures or beta exposures are significant for cases of skin cancer, 

however if high-energy (> 1.0 MeV) electrons are encountered, high exposures can be 

significant for breast and testicular cancer. For purposes of this guide, all discussions are 

applicable to skin cancer only. Most workers were somewhat protected from electron 

exposures through the use of coveralls, gloves, or other anti contamination clothing. Low 
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November 21, 2007 3 OCAS-IG-001 

energy electrons usually do not have sufficient energy to penetrate outer clothing, 

however exposed skin on the hands and face can receive significant exposure. 

For skin cancer, the dose should be estimated for the cancer site. If the cancer started on 

the hand, then the extremity dose would be more appropriate than the film badge worn on 

the lapel. Conversely, for skin cancer originating on the face, the lapel dosimeter would 

be more appropriate for determining the dose. Professional judgment should be used to 

determine which measurements are most appropriate for the skin cancer site. 

2.3.1 Dosimeter Dose 

2.3.1.1 Background 

Early practices of shallow dose conversion did not accurately reflect actual skin 

exposure. The open window of the film dosimeters was typically calibrated in units of 

exposure (R) using uranium, however at some facilities, an Sr-90/Y-90 source was used. 

2.3.1.2 Method 

As with photon and neutron exposures, the dosimeter dose is the simple summation of 

each dosimeter for a given year. The exposure is assumed to be equal to the shallow dose 

(H’(0.07)), recognizing that this is an overestimation of the true shallow dose. 

2.3.1.3 Uncertainty 

There has been very little published about the uncertainty of beta dosimetry. Considering 

the similar mechanisms between photon and beta film dosimetry, the methodology 

discussed in section 2.1.1.3 should be applied. 

2.3.2 Missed Dose 

2.3.2.1 Background 

 The combination of doses below the limit of detection in conjunction with early 

reporting criteria can result in significant missed dose. 

2.3.2.2 Method 

The missed dose will be calculated using the same method as that for photon and 

neutrons. 

2.3.2.3 Uncertainty 

The uncertainty for missed electron exposures is also assumed to follow a log normal 

distribution. 
 

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2.3.3 Skin Contamination 

2.3.3.1 Background 

Skin contamination can result in significant exposures. While frisking out of 

contamination areas, some workers might have triggered alarm levels such that 

decontamination of the skin was necessary. These skin contamination incidents have 

typically been recorded in the individual’s radiological exposure records. 

2.3.3.2 Method 

2.3.3.2.1 Location of Contamination 

To be included in the skin dose, the contamination must have occurred on a body part 

where the skin cancer originated. 

2.3.3.2.2 Dose Calculation 

For calculating the dose from skin contamination, a program such as VARSKIN1

 can be 

used to estimate the skin dose. The default skin depth should be 0.07 mm. If the area of 

the skin cancer is known, the dose should be calculated for that surface area. If the skin 

cancer area is unknown, the contamination area, if known, should be assumed to be the 

surface area of the skin cancer, however the surface area should not be less than 1 cm2

. 

The shielding effect of any personal protective equipment such as coveralls, gloves, 

plastics, etc. worn should be considered if known. 

2.3.3.3 Uncertainty 

When conducting dose reconstruction for skin cancer, there are multiple parameters 

which must be taken into consideration such as the activity, average area of the 

measurement probe, average area of the actual contamination, etc. Professional judgment 

should be used to determine the most probable exposure parameters in arriving at the 

central tendency of the log normal distribution of the dose. The maximum or 95% dose 

limit should be calculated assuming the most reasonable claimant friendly assumptions 

such as a minimum surface area of 1 cm2

, no protective clothing, negligible distance 

between contamination and skin, etc. 

3.0 EXTERNAL DOSE RECONSTRUCTION – INCOMPLETE, MISSING OR NO 

MONITORING DATA 

Incomplete or missing personal monitoring usually occurs either between two periods of 

monitoring data or at the beginning or end of a monitoring time period. When personal 

monitoring data is missing between two other periods of monitoring, interpolation 

between the two-monitored time periods may be reasonable. When the incomplete data 

is either before or after monitoring data, extrapolation may be reasonable, however 

caution should be used to properly account for any trends that may exist. 

1

 This is not an endorsement of the VARSKIN program, and is presented as one example of a typical 

program that could assist in skin dose computations. 
 

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November 21, 2007 3 OCAS-IG-001 

3.0.1 Interpolation of Missing Personal Monitoring Data 

In some instances, dosimetry records might be missing for a portion of an individual’s 

work history. However if the individual has sufficient monitoring data prior to and after 

the missing data, the dose can be interpolated by a simple average between the two 

monitoring periods. The interpolation would be considered reasonable providing the 

work practices, radiological protection measures, and the administrative and engineering 

controls did not change. In addition, interpolation may be conducted only if there is no 

indication, whether from the claimant or site radiological records, that a radiological 

incident resulting in a higher exposure occurred during the time period of missing data. 

3.0.2 Extrapolation from Incomplete Personal Monitoring Data 

At some sites, as the radiological monitoring practices were being developed, early 

dosimetry was rather crude and not all external radiation types were measured. As 

radiological monitoring programs became more sophisticated, more radiation types and 

energies were measured and recorded in personal monitoring records. Most programs 

started with measurements of high-energy photons and then added beta or electron 

measurements followed by neutrons. In order to reconstruct an individual’s dose during 

these early time periods, some extrapolation from adjacent (near-by) time periods may be 

necessary. Caution must be used, however, to account for trends in exposure data 

resulting from differences in work practices, implementation of radiological, 

administrative, and/or engineering controls that might change the exposure pattern. 

Uncertainty from either interpolation or extrapolation could be very difficult to accurately 

determine. Therefore claimant friendly upper bounds should be used. 

3.0.3 No Personal Monitoring Data 

When no personal monitoring data is available, the external radiation dose should be 

reconstructed based on 1) co-worker data, 2) radiation survey data or 3) source term 

information. As noted in section 1.4, Dose Reconstruction - Hierarchy of Data, coworker data should be used prior to radiation surveys and survey data should be used 

before source term information. It should be recognized that dose reconstructions based 

on survey data will probably be biased, since monitoring practices tended to be recorded 

at the highest level to ensure compliance, but this is an acceptable bias in a claimant 

friendly compensation program. If no survey data is available, the dose should be 

estimated based on the activity of the source term, engineering and administrative 

controls, and work history. 

3.1 Photon Exposures 

3.1.1 Photon Dose Reconstruction – Co-worker Data 

At some facilities, only a subset of workers was monitored for radiation exposure to 

demonstrate compliance with orders or regulations. In these instances, the claimant has 

been asked during the CATI for a list of co-workers who worked with the claimant. Data 

from the claimant’s co-worker(s) should be used when monitoring data is incomplete or 

missing. In some instances, multiple co-workers were monitored and an average was 

reported for the remainder of the group. The benefit of the doubt should be given to the 
 

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November 21, 2007 3 OCAS-IG-001 

claimant and the maximum reasonable worker dose within the group should be used. 

Since dosimetry data is being used, the methods discussed in Section 2.1 should be used 

for dose reconstructions. 

3.1.2 Photon Dose Reconstruction – Survey Data 

3.1.2.1 Background 

Throughout the history of radiological operations, radiation surveys using ionization 

chambers, Geiger-Mueller detectors, and scintillation detectors have been conducted on a 

routine basis at most weapons production plants. These data have typically been reported 

in radiation survey reports or on radiation work permits in units of exposure rate or dose 

rate such as mR/hr, mrem/hr, etc. These data, in conjunction with the duration of 

exposure, should be utilized only when personal monitoring data is not available, 

however they should be used before source term data. 

3.1.2.2 Method 

The exposure or dose can be calculated by simply multiplying the exposure or dose rate 

by the duration of exposure or dose. 

Dose & = D × t 

Exposure rate, in units of roentgen per hour (R/hr), has been reported on most early 

survey data sheets. In later years, when dose rate was reported, some consideration for 

the method of calibration of the instrument is necessary, although most will be ambient 

dose equivalent. Also, caution should be used to ensure the reported dose is not a 

shallow dose (i.e. open window). 

From area survey data, the exposure rate was generally well known and access to areas 

with very high exposure rates was typically restricted. In addition, since most 

radiological jobs do not result in exposure 8 hours a day, 5 days a week and 50 weeks per 

year, time is one of the most important variables. 

3.1.2.3 Uncertainty 

Generally, when using survey data for dose reconstruction there are only two variables, 

the distribution of measurements in the work area, and the duration of the exposure. 

Unlike dosimetry measurements, the uncertainty associated with survey data will tend to 

result in rather large standard deviations. If a normal distribution were used, the lower 

bound could be less than zero in some cases. Since sampling is conducted for the final 

distribution, the log normal distribution is believed to be the most reasonable uncertainty 

distribution based on survey data. 
3.1.3.2.1 Source Term 

 

 

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3.1.3 Photon Dose Reconstruction – Source Term 

3.1.3.1 Background 

Dose reconstruction from a source term is relatively difficult and the associated 

uncertainty is relatively large. Before conducting a dose reconstruction based on source 

term data, an investigation should be conducted to determine if the process is sufficiently 

similar to another operation at a monitored facility such that other worker data or survey 

data could be used to estimate workplace exposure levels. When worker and survey data 

are not available and source term data is used for the dose reconstruction, all assumptions 

and parameters used in the calculation must be clearly stated and documented in the dose 

reconstruction report. 

3.1.3.2 Method 

The source term (S) can sometimes be determined through process or material receipt 

records, if available. However, facility-handling information is critical to determine the 

approximate time, distance, and shielding assumptions needed to adequately calculate a 

dose to a worker. 

Generally, more complex calculations are required to account for the effects of geometry, 

self-shielding, multiple shielding and buildup. 

Computer programs such as Microshield2

 can greatly facilitate the computations from 

source term information. In addition, these programs also enable some worst-case 

examples to be developed to bound the uncertainty of the most reasonable estimate. 

Received 

With knowledge of density, purity, isotopic content, weight and/or dimensions of the 

material, the quantity of activity can be calculated from health physics first principles. 

3.1.3.2.2 Average Energy 

Most radionuclides emit multiple gamma and x-rays at varying yields per disintegration. 

Since IREP uses three photon energy intervals and five neutron energy intervals, the 

energy of the emissions can be grouped accordingly and the yields determined by group. 

3.1.3.2.3 Time of Exposure 

As with the survey data dose reconstruction, the time or duration of the exposure is one 

of the most critical factors to be estimated. As with dose reconstruction using survey 

data, specific information on duration of exposure expressed as hours per day, days per 

week, and weeks per year will assist in a more accurate estimate of exposure duration. 

2

 This is not an endorsement of the Microshield program, and is presented as one example of a program that 

could assist in the dose computations. 
Effective Date: Revision No. OCAS Document No. Page 28 of 77 

November 21, 2007 3 OCAS-IG-001 

3.1.3.2.4 Distance from Source 

The distance is another important parameter in estimating exposure to a radioactive 

material. At some facilities, workers were separated by tens of feet from radioactive 

materials due to engineering or administrative controls, while at other facilities, workers 

handled radioactive materials in bench top experiments such that the distance from the 

source was approximately 18 inches. 

3.1.3.2.5 Shielding 

For high-level sources, shielding was generally used as an engineering control to protect 

workers from excessive radiation exposure. In addition, some high-density radioactive 

materials such as uranium also shield a significant portion of the photons emitted. 

3.1.3.3 Uncertainty 

Dose uncertainty from source term estimates is relatively large. The most reasonable 

parameters of source strength, average distance, exposure duration, and shielding should 

be used to compute the most likely dose. Each of these parameters should then be 

reasonably estimated to maximize the dose (claimant friendly). Assuming a normal 

distribution, the most likely estimate should be the mean with the upper 95% limit being 

the claimant friendly estimate. 

3.1.4 Photon Dose Reconstruction – Control Limits 

3.1.4.1 Background 

Dose reconstruction based only on administrative or radiological monitoring controls will 

result in a gross overestimation of the claimant’s dose. Unfortunately, if no monitoring 

records of any type can be found and the source term is unknown, an upper external dose 

estimate can be developed using occupational radiation protection limits. This of course 

assumes that appropriate controls were in place to prevent exposures in excess of 

occupational limits. When conducting a dose reconstruction using control limits, all 

assumptions must be clearly stated in the dose reconstruction report. 

3.1.4.2 Method 

There are three radiological control limits that can be used for dose reconstruction: 

threshold for required monitoring; radiation posting limits; and annual radiation dose 

limits. 

3.1.4.2.1 Monitoring Not Required 

This method is most appropriate for office workers who were not monitored due to the 

low potential for exposure. In these instances, the central point estimate should be the 

threshold level for monitoring. At most facilities, this value was 100 mrem/year. 

3.1.4.2.2 Posted Control Limits 

This method is most appropriate for short duration exposures when an unmonitored 

person entered a radiological controlled area without proper monitoring. In these 

instances, the midpoint dose rate between posted areas should be used as a reasonable 
 

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November 21, 2007 3 OCAS-IG-001 

estimate. This midpoint dose rate multiplied by the number of hours of exposure will 

provide the central dose estimate. The upper bound of the posted area multiplied by the 

number of hours in the areas will result in the upper 95% dose estimate. 

3.1.4.2.3 Annual Radiation Dose Limits 

The dose assigned is the maximum allowable monthly dose times the number of months 

worked. Since a worker could have received the annual limit in a short time frame, the 

acute exposure should be used. Since dose reconstruction using annual limits will yield 

unreasonably large exposure estimates some restrictions apply to the use of annual limits. 

The method should only be used for short employment durations of less than one year. 

3.1.4.3 Uncertainty 

As indicated in section 3.1.3.4, the midpoint of the dose range should be used as the most 

likely estimate with the maximum being the upper 95% of a lognormal distribution. 

Although DOE orders have specified, weekly, monthly, and quarterly dose limits, 

workers have been allowed to exceed these administrative limits as long as they did not 

exceed the annual limits. Generally the central estimate a dose distribution can be 

developed using the weekly, monthly, or quarterly exposure limit with the upper 95% 

confidence interval being the annual radiation dose limit. However, when the annual 

radiation dose limit is used for dose reconstruction, this dose should be considered the 

maximum dose. Therefore a constant should be used and thus there is no distribution. 

3.2 Neutron Exposures 

As with photon exposures, estimating neutron exposures without personal monitoring 

data is relatively difficult. The use of neutron to photon ratios is an acceptable method to 

assign a neutron dose to workers using site-specific data. Co-worker data, survey data, 

and/or source term data are useful in the determination of neutron exposures. 

3.2.1 Neutron Dose Reconstruction - Co-worker Data 

After individual monitoring data, co-worker data is considered the next most accurate 

indicator of exposure. This data should be used whenever individual monitoring data for 

the claimant is not available. When job category (co-worker) data is available, the 

benefit of the doubt should be given to the claimant and the maximum reasonable worker 

dose within the job category should be used. Since dosimetry data is being used, the 

methods discussed in Section 2.2 should be used for dose reconstruction from co-worker 

data. 

3.2.2 Neutron Dose Reconstruction – Survey Data 

3.2.2.1 Background 

Neutron monitoring has been conducted using proportional counters such as BF3 

detectors and recently, tissue equivalent proportional counters (TEPC). Around nuclear 

reactors, neutron measurements have been conducted to verify adequate shielding of the 

reactor, thus survey data should be available to estimate exposures. 
 

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November 21, 2007 3 OCAS-IG-001 

3.2.2.2 Method 

The general equation is the same as described in section 3.1.2 and is provided as follows. 

Dose & = D × t 

where: D& = dose rate or fluence 

t = duration of the exposure 

Generally, an average of the dose rate measurements in the workplace should be used for 

the central estimate. 

3.2.2.3 Uncertainty 

As with most exposure discussions in this guide, the central estimate should be an 

average of the survey data. The upper bound should be estimated by applying the 

maximum work time period with the maximum recorded dose rate for the area. 

Generally, survey data follow a lognormal distribution, therefore this distribution should 

be used for the uncertainty distribution. In addition, since the uncertainty is expected to 

be relatively large, a significant percent of the data could be negative if a normal 

distribution were used. 

3.2.3 Neutron Dose Reconstruction - Source Term Data 

3.2.3.1 Background 

Dose reconstruction from a neutron source term should only be conducted when no 

survey data is available and relatively simple exposure geometries are appropriate. 

NCRP 38 (1971) provides general guidance for radiological protection against neutron 

radiation. 

3.2.3.2 Method 

This methodology described in NCRP 38 (1971) should be used when estimating neutron 

exposures from various shielded sources. The general point source equation is similar to 

the photon point source equation in section 3.1.3, however the attenuation coefficient is 

replaced with a neutron removal cross section. NCRP 38 discusses criteria for which the 

removal cross section is a valid assumption. 

Additional removal cross sections can be calculated using the methodology discussed in 

NCRP (1971) Report 38. 

3.2.3.3 Uncertainty 

The uncertainty associated with dose estimation from source term data is relatively large 

and could vary by an order of magnitude or more. As with the photon measurements 

there are several sources of uncertainty; including the duration of the exposure, the 

distance from the source, variations in the shielding thickness, and the uncertainty of the 

initial neutron fluence. The most reasonable value of each parameter should be used to 
 

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November 21, 2007 3 OCAS-IG-001 

determine the central estimate, while claimant friendly assumptions should be made to 

estimate the upper bound of the distribution. Generally, a normal distribution should be 

applied, however if the upper bound uncertainty (2σ) subtracted from the central estimate 

is less than zero, a lognormal distribution should be used. 

3.3 Electron Exposures 

Electron exposures are only important for certain cancer sites such as the skin, breast, and 

possibly for the testes, depending on the electron energy and shielding. Electron 

exposures do not need to be calculated for deep organs. 

In the absence of co-worker data, survey data can be used. Source term data can also be 

used. Generally, administrative dose limits for skin exposures are very large, however 

contamination control limits could be used to estimate the upper bound of low-level 

exposures for initial dose assessment. 

3.3.1 Electron Dose Reconstruction - Co-worker Data 

 Generally whole body dosimetry would be a good measure of exposure. Differences in 

job functions, proximity to the source and duration of exposure make extremity 

dosimetry highly uncertain and should not be used, unless the identical job function is 

performed, and the proximity to the source is identical and relative fractions of exposure 

time can be clearly established. 

3.3.2 Electron Dose Reconstruction - Survey Data 

3.3.2.1 Background 

Open window GM detectors or thin window ionization chambers have been used to 

measure the beta dose rate, however, in some instances, only contamination survey data 

is available in units of activity. The method section is subdivided into dose rate surveys 

and contamination surveys. 

3.3.2.2 Method 

3.3.2.2.1 Electron Dose Rate Data 

Electron or beta dose rate survey data in conjunction with duration of exposure can be 

used to estimate electron dose, using the standard equation discussed in section 3.1.2 and 

3.2.2. 

Dose & = D × t 

where: D& = dose rate usually in mrad/hr 

t = duration of the exposure 

3.3.2.2.2 Contamination Survey Data 

In some instances contamination survey data could be used to estimate the beta dose rate. 

For these computations, the computer program VARSKIN may be used as it integrates 
 

 

 

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November 21, 2007 3 OCAS-IG-001 

the Berger (1971) point kernel equation. The computational methods and details can be 

found in NUREG/CR-5873 (Durham, 1992). Basic inputs to VARSKIN include source 

geometry, activity, source size, air gap, protective layer thickness, and density of the 

protective layer. While the VARSKIN program was designed for skin contamination, by 

varying the air gap, it can be utilized for external electron skin doses. When utilizing 

contamination survey data, a large disc source is recommended and minimum averaged 

dose area should be no less than 1 cm2

. 

3.3.2.3 Uncertainty 

As with previous uncertainty calculations, the average reading or most likely reading for 

dose rate measurements or activity measurements should be used as the central estimate. 

The highest recorded value should be used to calculate the upper 95% bound. The 

duration should also be varied to determine the upper 95% bound of the log normal 

distribution. 

3.3.3 Electron Dose Reconstruction - Source Term 

3.3.3.1 Background 

This type of dose reconstruction should not be conducted unless detailed information 

about the source, encapsulation, duration of exposure or contamination levels are known 

or can be adequately bounded. The most applicable scenario would be to use this method 

for unencapsulated bare metal such as uranium. 

3.3.3.2 Method 

As with the surface contamination methodology, the skin dose rate can be calculated 

from various geometries using source term activity and a program such as VARSKIN. 

The dose rate can be combined with exposure time to calculate the central dose estimate 

as shown in the following equation. 

Dose & = D × t 

where: D& = dose rate usually in mrad/hr 

t = duration of the exposure 

3.3.3.3 Uncertainty 

As with other source term dose reconstructions, the time, distance, and shielding can be 

varied to develop the upper dose limit. The electron dose distribution is assumed to 

follow a log normal distribution. Professional judgment should be used to estimate the 

most probable exposure, with claimant friendly and clearly stated assumptions, such as 

no shielding, close distance and maximum exposure time to estimate the 95% upper dose 

limit. For multiple skin contamination incidents in a single year, the uncertainty should 

be combined using the square root of the sum of the squares methodology as described in 

section 2.1.1.3.4. 
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4.0 CONVERSION TO ORGAN DOSE 

The purpose of this section is to provide guidance on the conversion from individual 

monitoring data to organ dose. For photon exposures, the organ dose conversion 

coefficients in ICRP 74 convert from free-air KERMA to absorbed dose in the organ of 

interest. A conversion from monitored dose to free-air KERMA is needed to complete 

the organ dose conversion. Neutron organ dose conversion factors in ICRP 74 are 

tabulated per neutron fluence. While some monitoring data has been reported in terms of 

fluence, traditionally, neutron doses have been reported as either ambient dose at 10mm 

(H*

(10)) or personal dose at 10 mm (Hp,slab(10)). Since skin is the primary target tissue 

for electron doses, the dose conversion factors should be calculated for a skin depth of 

0.07 mm. 

The assumption of a 100% AP exposure geometry, together with the corresponding AP 

DCFs in APPENDIX A, does not, in general, result in an underestimate of organ dose in 

the great majority of cases. There is a relatively small percentage of cases for which 

organ dose underestimates could occur if the true exposure geometry was not 100% AP. 

It is recommended that any modification be based on a dosimeter location adjustment 

factor (see Table 4.1a), rather than adjusting the organ DCF in APPENDIX A. However, 

if a default assumption of 100% AP exposure geometry is deemed inappropriate, it can be 

shown that application of dosimeter location adjustment factors would actually reduce the 

dose estimate for many organs compared to the current approach (ORAU 2005). It is 

therefore recommended to use a dosimeter location adjustment factor on DCFs associated 

with those organs for which rotational and isotropic geometries are predominantly 

claimant favorable. Four organs have DCF’s for which ISO or ROT geometries are 

generally 10% or more favorable. Correction factors for the appropriate geometries are 

listed section 4.4. 

The relative angular response of the dosimeter with respect to the incident beam is of 

little significance for un-filtered film or TLD’s, so long as the mean free path of the 

photon or beta particle is greater than the absorber (Attix 1966). Hence open-window 

readings can generally be considered independent of exposure angle. Lower energy 

photons (<250 keV) are affected the most by angle and filtration thickness, with the 

reduction in response proportional to the cosine of the incidence angle. However, for 

energies < 30keV the open-window is the region of interest for shallow dose and is 

independent of angle. Therefore, the energy range between 30 keV and 250 keV has the 

greatest variability for each filtered portion of the film/TLD and must be addressed in the 

dose reconstruction. How this is done will rely on the job performed and the types of 

radiation involved. Specific guidance on orientation is found in the individual site 

Technical Basis Document. 

4.1 Photon Dose 

The two basic types of data involved in converting photon doses to organ dose are 

monitored individual doses, and survey or source term dose rate data. 
 

 

4.1.1 Development of the Monitored Exposure/Dose to Organ dose factor 

4.1.1.1 Exposure (R) to free-air KERMA (Ka) 

Most early monitoring data was reported in units of exposure and not a deep dose at 10 

mm. Using figure 4.3 in ICRU 43 (1988), and the ambient deep dose (H*(10)) from 

ICRP 74 (1996), the conversion factor from exposure to free-air KERMA can be 

calculated. Table 4.1 provides the conversion factors used in calculations to develop the 

organ dose conversion factors. 

→ KE a K a

H ×= * (10) 

H * (10) 

1 

K a

E =

E 

where 

E = Exposure

10 )H * ( = Ambient Dose

K a = free − air KERMA

Table 4.1 Conversion factors used in organ dose calculations. 

Photon Energy 

(MeV) 

Ambient Dose Equivalent 

H*(10) - cSv 

Exposure (R)(1) 

Ambient Dose Equivalent 

H*(10) - cSv 

free-air KERMA (Ka)

(2) 

Exposure (R) 

free-air KERMA (K

0.015 0.25 0.26 1.04

0.020 0.60 0.61 1.02

0.030 1.00 1.10 1.10

0.040 1.30 1.47 1.13

0.050 1.46 1.67 1.14

0.060 1.55 1.74 1.12

0.070 1.53 1.73 1.13

0.080 1.51 1.72 1.14

0.100 1.43 1.65 1.15

0.150 1.30 1.49 1.15

0.200 1.20 1.40 1.17

0.300 1.13 1.31 1.16

0.400 1.09 1.26 1.16

0.500 1.05 1.23 1.17

0.600 1.04 1.21 1.16

0.800 1.01 1.19 1.18

1.000 1.00 1.17 1.17

2.000 0.96 1.14 1.19

4.000 0.95 1.12 1.18

6.000 0.95 1.11 1.17

8.000 0.95 1.11 1.17

10.000

(1) 

 0.95 1.10 1.16

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November 21, 2007 3 OCAS-IG-001 

Data extracted from Figure 4.3 ICRU 43 (1988) 

(2) Data from ICRP 74 (1996) 

a) 
 

 

 

 

 

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4.1.1.2 Photon Dose Equivalent H*(10) and Hp(10) to free-air KERMA 

Table A.21 in ICRP 74 (1996) lists the conversion coefficients from ambient dose 

equivalent (H*(10)) to free-air KERMA (Ka) by photon energy. Table A.24 in ICRP 74 

(1996) lists the conversion coefficients from personal dose equivalent (Hp(10)) to air 

KERMA (Ka). Once the dose is converted to free-air KERMA, the organ dose is a 

straightforward multiplication of the dose conversion factors (DT/Ka) listed in Tables A.2 

– A.20 of ICRP 74 (1996). 

1 DT DCF Hp(10)→D = × T H p (10) Ka 

Ka 

where: 

DT = Absorbed Dose in Target Tissue 

H p (10) = Personal Dose Equivalent 

K a = free - air KERMA

4.1.2 Area survey or source term data to Organ Dose 

Generally, radiation survey data have been reported in units of exposure (R) in free air. 

For these data, the exposure methodology discussed in section 4.1.1.1 should be used. 

Area survey dose rates or those calculated from source term information should generally 

be assumed to be the ambient dose at 10 mm or H*

(10). 

4.1.3 Dose Conversion Factor Simplification 

The Dose Conversion Factors (DCF) in ICRP 74 are listed by tissue of interest, exposure 

geometry, and radiation energy. As noted previously, NIOSH-IREP uses energy intervals 

for the probability of causation calculation. Since ICRP 74 lists the dose conversion 

factor for multiple energies, some simplification is needed for dose reconstruction under 

EEOICPA. As shown in Figure 4.1, the dose conversion coefficient is a continuous 

function of energy. For simplification, the area under the curve from the beginning to the 

end of the energy interval divided by the range will be used as the simplified dose 

conversion coefficient. A simple function (f(E)) was fitted for each energy interval to 

integrate the area under the curve. The example below is for red bone marrow dose from 

photons between 30 and 250 keV. 

250 

f (E)dx ∫

30 Bone Marrow - Gy DCF = = 0.479 γ ,30−250keV Range Hp (10) Gy 
Dose Conversion Factor 

(Bone Marrow Dose/ Hp(10))

0.900 

0.800 

0.700 

0.600 

0.500 

0.400 

0.300 

0.200 

0.100 

0.000 

0.479 

0.746 

0.030 

0.010 0.100 1.000 10.000 

Photon Energy (MeV) 

 

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Figure 4.1 Chart of red bone marrow Dose Conversion Factor (DCF) versus photon 

energy, fitted curve, and associated simplified dose conversion factor for energy band. 

Appendix A lists the simplified dose conversion factors by reporting unit (exposure, 

ambient dose (H*

(10)), or personal dose equivalent (Hp(10))) for the three photon energy 

bands. It should be noted that the upper bound used in the calculation of the high-energy 

group for photons is truncated at 6 MeV. This method was employed since there are very 

few operations at DOE which result in photon exposures greater than 6 MeV. 

4.2 Neutron Dose Conversion 

4.2.1 Area Monitoring Data to Organ Dose 

Area monitoring data has been reported in several different formats. Some earlier 

measurements report the fluence, with energy information provided, while other 

measurements are reported in absorbed dose (rad), or dose equivalent (rem). 

4.2.1.1 Fluence Data to Organ Dose 

When fluence data are provided, the conversion to organ dose is straightforward using 

tables A.26 through A.40 in ICRP 74 (1996). As with the photon dose conversion 

factors, the ICRP 74 (1996) tables have been compressed into the five neutron energy 

intervals for use in the IREP program. These compressed tables can be found in 

Appendix A of this guide. 

4.2.1.2 Ambient Dose (H*(10)) to Organ Dose Equivalent 

When ambient dose (HS

*

(10)) has been reported (typically in survey data), the site 

specific quality factor (Qs) must be removed such that absorbed dose is the fundamental 

unit. Current ICRP 60 (1990) radiation weighting factors (wR) should then be multiplied 

by the absorbed dose to develop the standard ambient dose equivalent (H*(10)). From 
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November 21, 2007 3 OCAS-IG-001 

the standard ambient dose equivalent the conversion factors in Appendix A are then 

applied to determine organ dose equivalent. The conversion from site specific ambient 

dose to organ dose is illustrated in the following equation. 

* HS (10 ) H T = × w R × DCF * HT / H (10 ) QS 

4.2.2 Personal Monitoring Data to Organ Dose 

When routine personal monitoring began, the reported quantity has usually been in dose 

equivalent. Currently, the standard for personal monitoring neutron data is the personal 

dose equivalent at 10 mm calibrated using the ICRU slab phantom (Hp,slab(10)). 

4.2.2.1 Neutron Dose Equivalent (Hp,slab(10)) to Organ Dose Equivalent 

Appendix A lists the personal dose equivalent to organ dose equivalent conversion 

factors. As with the ambient dose, the site specific quality factor (QS) should be removed 

prior to dose calculations and the ICRP 60 (1990) weighting factor (w

4.2.3 Special Dose Conversion Factor for Plutonium 

R) applied before 

the conversion to organ dose. 

Organ dose conversion factors are tabulated by averaging the energy specific values from 

ICRP 74 (1996) over the IREP photon energy range. The lowest photon energy interval 

in Interactive RadioEpidemiological Program (IREP) is categorized as less than 30 keV. 

Plutonium emits several x-rays in this energy range; however, a simple average as used in 

the previous sections may not result in the most accurate dose conversion factor. For 

Plutonium work, the average x-ray energy is approximately 17 keV. As a result, using 20 

keV as a claimant favorable single point estimate is appropriate. Since the low energy 

photon dose from glove box work, for example, is predominately in the anterior-posterior 

(AP) geometry, single point estimate values were calculated for 16 organs listed in ICRP 

74. When estimating the low energy photon organ dose, the values in Table 4.1a should 

be used. 
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November 21, 2007 3 OCAS-IG-001 

Table 4.1a Special Dose Conversion Factors (DCF's) for Plutonium. 

These were calculated assuming AP geometry and 20 keV mono-energetic 

photons. 

Organ 

Personal Dose 

Equivalent 

(Hp(10)) – Organ 

Dose (HT) 

Ambient Dose 

Equivalent 

(H*(10)) – Organ 

Dose (HT) 

Exposure (R) – 

Organ Dose (HT) 

Bladder 0.146 0.147 0.088 

Bone (Red 

Marrow) 0.024 0.024 0.014 

Bone (Surfaces) 0.165 0.166 0.099 

Breast (Female) 0.761 0.762 0.457 

Colon 0.024 0.024 0.015 

Esophagus * * * 

Eye 1.493 1.495 0.897 

Ovaries * * * 

Testes 0.823 0.825 0.495 

Liver 0.068 0.069 0.041 

Lung 0.050 0.050 0.030 

Remainder 0.053 0.053 0.032 

Stomach 0.144 0.144 0.087 

Thymus 0.264 0.264 0.158 

Thyroid 0.586 0.587 0.352 

Uterus 0.002 0.002 0.001 * 20 keV values not listed in ICRP 748

 – Use < 30 keV DCF’s from OCAS-IG-0017or an appropriate 

surrogate organ 

4.3 Electron Dose Conversion Factors 

ICRP 74 (1996) list energy specific organ dose conversion factor from fluence. It is 

anticipated that relatively few dose measurements will have been reported in this manner. 

ICRP 74 indicates that the dose conversion factor is highly dependant on the electron 

energy. Since most electron exposures will be a continuum of energies, the site-specific 

dose conversion factor should generally be used. The shallow dose at 0.07 mm can be 

assumed to be the skin organ dose. 

4.4 Exposure Energy and Geometry 

There are six basic exposure geometries discussed in ICRP 74 (1996); the anterior to 

posterior (AP), posterior to anterior (PA), left lateral (LLAT), right lateral (RLAT), 

rotational (ROT) and isotropic (ISO) (Figure 4.2). Of these, only four (AP, PA, ROT, 

and ISO) are of primary interest in dose reconstruction. The AP geometry is typically the 

most representative geometry experienced by workers because the source of radiation is 

directly viewed and relatively closer to the worker. However, there are specific job 

functions in certain types of facilities, which would tend to lead to a different geometry. 
 

 

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The AP DCF values in Appendix A are not the most claimant favorable for bone 

(surface), bone (red marrow), esophagus, and lung when the dosimeter is worn on the 

chest. For these organs, if the dosimeter is worn on the chest, multiply the Appendix A 

values of ROT and ISO by the factors in Table 4.1a instead of using the AP value. In 

these cases, the ROT or ISO geometries are more claimant favorable than the AP value in 

Appendix A. However, the correction factors need not be applied if it is determined that 

the most representative geometry is 100% AP or other compensating claimant favorable 

determinations have been made in dose reconstruction. 

Table 4.1a Correction factors for ROT and ISO DCF values for Bone (RM and Surf), Esophagus, and Lung 

Photon Energy Range Rotational Conversion Factor Isotropic Conversion. Factor 

30-250 keV 1.45 1.58 

> 250 keV 1.18 1.28 

Note 1: Based upon dosimeter location being on the chest. 

Note 2: Based upon dosimeter correction factors in Thierry-Chef (2002) 

4.4.1 Dosimeter and Missed Dose Geometry 

For dose reconstruction, professional judgment should be used to determine the most 

credible geometry or geometry weighting factors (wg) from multiple geometries based 

upon an individual’s work history and the CATI. The work-related Dose Conversion 

Factor (DCFW) should be calculated as follows: 

DCF W AP AP PA PA ROT ROT ISO ISO = w DCF + w DCF + w DCF + w DCF

Figure 4.2 Exposure geometries of an anthropomorphic phantom extracted from ICRP 74 

(1996) 

For example, the isotropic geometry would be reasonable for a general laborer in a 

uranium manufacturing storage facility, while a lathe worker in the same facility would 

be more likely to receive the majority of their exposure in an anterior-posterior fashion. 

A reactor worker refueling a graphite reactor would likely receive their exposure in both 

the AP and ROT geometry. Table 4.2 provides some general guidance on percentages of 

exposure geometries. 
Facility Job Geometry Percentage

Uranium Facility 

 

General Laborer ISO 75% 

AP 25%

Machinist AP 75%

 ISO 25%

 

Supervisor AP 50%

ISO 50%

Reactor Fuel Handler AP 50%

 ROT 50%

 

Reactor Operator ROT 75%

ISO 25%

Chemical Separations 

 

Glovebox Chemist AP 90% 

ROT 10%

Maintenance Worker AP 50%

 ROT 50%

 

Security Guard ROT 50%

ISO 50%

 

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November 21, 2007 3 OCAS-IG-001 

Table 4.2 Common exposure geometries for various jobs and facilities. 

4.4.2 Occupational Medical Exposure Geometry 

Generally, the exposure geometry for occupational medical chest x-ray exposures is the 

PA geometry. There are, however, other screening procedures in which the exposure 

geometry will be different and these should be applied as appropriate. 

4.4.3 Environmental Exposure Geometry 

The exposure geometry for environmental doses is almost always isotropic in nature. 

This assumption should be applied to all environmental doses unless another geometry is 

more appropriate and has been clearly justified. 

4.5 Dose Conversion Uncertainty 

4.5.1 Energy Uncertainty 

The uncertainty resulting from the energy simplification is assumed to follow a uniform 

distribution using the dose conversion factor lower and upper bounds within the energy 

interval for the specific exposure geometry. Table 4.3 provides an example using the 

bone marrow with the anterior-posterior geometry for photons (Figure 4.1). 

Table 4.3: Photon Bone Marrow Energy Uncertainty using AP geometry 

Photon Energy 

Band 

Effective Dose 

Conversion Factor 

Minimum Dose 

Conversion Factor 

Maximum Dose 

Conversion Factor 

< 30 keV 0.030 0.016 0.063 

30 – 250 keV 0.479 0.063 0.540 

> 250 keV 0.746 0.540 0.834 

4.5.2 Geometry Uncertainty 

There is often considerable uncertainty as to the position from which the claimant 

received radiation exposure. As noted in section 4.3, there maybe some information 

about job function and position of exposure when handling radioactive materials. Since 
 

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November 21, 2007 3 OCAS-IG-001 

the “true” exposure geometry is almost never known, an uncertainty distribution about 

the dose conversion factor is appropriate. Since likely exposure geometry can be 

calculated for most jobs, a uniform distribution appears to be inappropriate. However, a 

triangular distribution with the effective DCF being the most likely geometry, the lower 

bound being the geometry that would result in the lowest organ dose (or dose conversion 

factor) and the upper bound being the geometry resulting in the highest organ dose 

(highest dose conversion factor) maybe appropriate. 

5.0 ANNUAL ORGAN DOSE & DISTRIBUTION 

5.1 Organ Dose Computation 

5.1.1 Organ Dose Estimate 

5.1.1.1 Background 

The main purpose of this section is to provide guidance on converting the measured dose 

into an organ dose and to combine each dose component into a single annual dose 

estimate for entry into the IREP program. 

5.1.1.2 Method 

The organ dose for each radiation type and energy are compiled by summing the organ 

dose components calculated by multiplying the dose or exposure component by the 

appropriate dose conversion factor. When multiple variations have been reported such as 

ambient dose equivalent and personal dose equivalent, the conversion should be 

conducted before the summation. The general equation is as follows: 

Dradiation,tissue = DD (DCFW ) + DM (DCF ) + DOM (DCF ) + DE (DCFISO W ) AP 

5.1.2 Uncertainty Distribution 

5.1.2.1 Background 

The uncertainty associated with the organ dose is computed through random sampling 

(Monte Carlo) of each distribution used to compute the central organ dose estimate. By 

using these distributions, the overall organ dose uncertainty can be determined with 

reasonable precision. For simple computations a minimum of 1000 iterations can be 

used, however, a larger number of iterations may be necessary to determine whether the 

tendency of the distribution is normal or lognormal. 

5.1.2.2 Method 

Since different exposure geometries are more appropriate for different dose components, 

the individual dose components (dosimeter dose, missed dose, occupational medical 

dose, and environmental dose) each must be converted to organ dose. The total radiation 
 

Effective Date: Revision No. OCAS Document No. Page 42 of 77 

November 21, 2007 3 OCAS-IG-001 

energy interval uncertainty is then calculated by sampling from each of the organ dose 

distributions. 

5.2 Dose Distribution Determination/Categorization 

The compiled distribution is likely to be either normally or log normally distributed. The 

tendency will most likely be highly dependent on the ratio between the missed dose (log 

normal distribution) and the dosimeter dose (normal distribution). Therefore some 

statistical test should be applied to determine which distribution is more appropriate. The 

statistical test can be conducted manually using any variety of methods or by using 

standard statistical software. Since the sampled dose distribution is likely not to fall 

strictly into one distribution or another, some professional judgment should be used to 

determine the best fit to the data. As Kumazawa (1988) found, low level doses tend to 

follow a log normal distribution while higher level doses near occupational exposure 

limits tend to follow a normal distribution. 

5.3 IREP-Excel Reporting Format 

To assist in probability of causation calculations, the annual dose information should be 

entered into the IREP-EXCEL spreadsheet. The format for this spreadsheet can be found 

in Appendix B of this guide. 
 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 43 of 77 

November 21, 2007 3 OCAS-IG-001 

6.0 REFERENCES 

1. Berger, M. J. (1971) Distribution of Absorbed Dose Around Point Sources of Electrons and Beta 

Particles in Water and Other Media, Journal of Nuclear Medicine, Vol. 12 (Suppl 5), pp. 5. 

2. Brodsky, A., Spritzer, A. A., Feagin, F. E., Bradley, F. J., Karches, G. J. and Mandelberg, H. I. 

(1965) Accuracy and Sensitivity of Film Measurements of Gamma Radiation - Part IV, 

Health Physics, Vol. 11 (10), pp. 1071. 

3. Cardarelli, J. J., Spitz, H., Rice, C., Buncher, C. R., Elson, H. and Succop, P. (2001), Significance 

of radiation exposure from work-related chest x-rays for epidemiologic studies of radiation 

workers, X2001 - Exposure Assessment in Epidemiology and Practice, M. Hagberg, B. 

Knave, L. Lillienberg and H. Westberg, ,Gothenberg, Sweden, National Institute for Working 

Life. 

4. Durham, J. S., (1992) Pacific Northwest Laboratory. VARSKIN MOD2 and SADDE MOD 2: 

Computer Codes for Assessing Skin Dose From Skin Contamination, NUREG/CR-5873, 

Pacific Northwest Laboratory, Richland, Washington. 

5. Finkelstein, M. M. and Verma, D. K. (2001) Exposure Estimation in the Presence of 

Nondetectable Values: Another Look, American Industrial Hygiene Association Journal, Vol. 

62 (2), pp. 195. 

6. Fix, J. J., Wilson, R. H. and Baumgartner, W. V., (1996) Battelle. Retrospective Assessment of 

Personnel Neutron Dosimetry for Workers at the Hanford Site, PNNL-11196, Pacific 

Northwest National Laboratory, Richland, Washington. 

7. Griffith, R. V., Hankins, D. E., Gammage, R. B. and Tommasino, L. (1979) Recent Developments 

in Personnel Neutron Dosimeters - A Review, Health Physics, Vol. 36 pp. 235. 

8. Heinzelmann, M. and Nachtigall, D. (1968) Effective and Average Neutron Energies of (,n) 

Sources Behind Hydrogen Containing Shielding, Health Physics, Vol. 15 pp. 87. 

9. Hirning, C. R. (1992) Detection and Determination Limits for Thermoluminescence Dosimetry, 

Health Physics, Vol. 62 (3), pp. 223. 

10. Hornung, R. W. and Reed, L. D. (1990) Estimation of Average Concentration in the Presence of 

Nondetectable Values, Applied Occupational and Environmental Hygiene, Vol. 5 (1), pp. 46. 

11. ICRP, (1996) International Commission on Radiological Protection. Conversion Coefficients for 

Use in Radiological Protection Against External Radiation, ICRP Publication 74, Annals of 

the ICRP Vol 26, Pergamon Press, Oxford, England. 

12. ICRP, (1990) Recommendations of the International Commission on Radiological Protection, 

ICRP Publication 60, Annals of the ICRP Vol 21, Pergamon Press, Oxford, England. 

13. ICRU, (1988) International Commission on Radiation Units and Measurements. Determination of 

Dose Equivalents From External Radiation Sources - Part 2, ICRU Report 43, International 

Commission on Radiation Units and Measurements, Bethesda Maryland. 

14. Langmead, W. A. and Adams, N. (1967) Investigations of the Accuracy Attained in Routine Film 

Badge Dosimetry, Health Physics, Vol. 13 pp. 167. 
 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 44 of 77 

November 21, 2007 3 OCAS-IG-001 

15. McDonald, J. C. and Hadley, R. T. (1985) Response Characteristics of Selected Personnel Neutron 

Dosimeters in Use at DOE Facilities, Radiation Protection Dosimetry, Vol. 12 (3), pp. 275. 

16. NCRP, (1971) National Council on Radiation Protection and Measurements. Protection Against 

Neutron Radiation, NCRP Report 38, National Council on Radiation Protection and 

Measurements, Bethesda, Maryland. 

17. NCRP, (1989) National Council on Radiation Protection and Measurements. Medical X-ray, 

Electron Beam and Gamma-ray Protection for energies up to 50 MeV (Equipment Design, 

Performance and Use), NCRP Report 102, National Council on Radiation Protection and 

Measurements, Bethesda, Maryland. 

18. NRC, (1989) National Research Council. Film Badge Dosimetry in Atmospheric Nuclear Tests, 

National Academy Press, Washington D.C. 

19. Office of the Federal Register, (2000) Occupational Radiation Protection, 10 CFR Part 835, 

National Archives and Records Administration, Washington D.C. 

20. Office of the Federal Register, (2001) Methods for Radiation Dose Reconstruction Under the 

Energy Employees Occupational Illness Compensation Program Act of 2000, 42 CFR Part 82, 

National Archives and Records Administration, Washington D.C. 

21. Oshino, M. (1973) Response of NTA Personnel Neutron Monitoring Film Worn on Human 

Phantom, Health Physics, Vol. 24 (1), pp. 71. 

22. Parker, H. M., (1947) Health Physics, Instrumentation, and Radiation Protection, MDDC-783, 

United States Atomic Energy Commission, Oak Ridge, Tennessee. 

23. Reddie, J. B. and Whipple, G. H., (1949) Fast Neutron Measurements - 234-5 Building, HW14440, Hanford Engineering Works, Richland, Washington. 

24. Schimmerling, W. and Sass, R. E. (1968) Experience with a Commercial film Badge Service, 

Health Physics, Vol. 15 pp. 73. 

25. Strom, D. J. (1986) Estimating Individual and Collective Doses to Groups with 'Less Than 

Detectable' Doses: A Method for Use in Epidemiologic Studies, Health Physics, Vol. 51 (4), 

pp. 437. 

26. Swinth, K. W., Rathbun, L. A. and Brackenbush, L. W. (1986) Beta Fields and Measurement 

Practices at DOE Facilities, Radiation Protection Dosimetry, Vol. 14 (2), pp. 105. 

27. Taulbee, T. D., Neton, J. W., Lennard, M. L. and Feng, H. A. (2001) An Evaluation of Models to 

Estimate Missed Dose in Retrosprective Dose Assessments, Health Physics, Vol. 80 (6 

Suppl), pp. S99-S100. 

28. Watson, E. C., (1959) A Review of the NTA (Fast Neutron) Film Program, HW-61008, General 

Electric, Richland, Washington. 

29. Thierry-Chef, I., Pernicka, F., Marshall, M., Cardis, E., Andreo, P. (2002) Study of a Selection of 

10 Historical Types of Dosemeter: Variation of the Response to Hp (10) with Photon Energy 

and Geometry of Exposure, Radiation Protection Dosimetry Vol. 102 (2), pp. 101-113. 

30. Hendee, (1967) Radiation Response of LiF at Low Doses, Health Physics 13,1235 
Effective Date: Revision No. OCAS Document No. Page 45 of 77 

November 21, 2007 3 OCAS-IG-001 

31. Wallace, Watkins, (1968) Radiation Response of LiF at Low Doses, Health Physics 15, 159 

32. ORAU, (2005) Technical Justification for the Use of 100% AP Organ Dose Conversion Factors as a Claimant 

Favorable Approach to External Dose Reconstruction, Draft 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 46 of 77 

November 21, 2007 3 OCAS-IG-001 

APPENDIX A – PHOTON DOSE CONVERSION FACTORS (DCF) 

Organ: Bladder 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.166 

(0.000-0.426) 

0.006 

(0.000-0.035) 

0.046 

(0.000-0.141) 

0.030 

(0.000-0.100) 0.000 0.426 

30 - 250 keV 0.873 

(0.426-0.914) 

0.419 

(0.035-0.500) 

0.491 

(0.141-0.553) 

0.379 

(0.100-0.432) 0.035 0.914 

>250 Kev 0.913 

(0.876-0.929) 

0.720 

(0.500-0.753) 

0.764 

(0.553-0.846) 

0.672 

(0.432-0.755) 0.432 0.929 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.168 

(0.000-0.431) 

0.007 

(0.000-0.036) 

0.046 

(0.000-0.143) 

0.030 

(0.000-0.101) 0.000 0.431 

30 - 250 keV 0.940 

(0.431-1.007) 

0.452 

(0.036-0.527) 

0.528 

(0.143-0.583) 

0.408 

(0.101-0.456) 0.036 1.007 

>250 Kev 0.911 

(0.885-0.947) 

0.719 

(0.527-0.751) 

0.763 

(0.583-0.855) 

0.671 

(0.456-0.763) 0.456 0.947 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.175 

(0.008-0.431) 

0.010 

(0.000-0.036) 

0.054 

(0.001-0.143) 

0.036 

(0.001-0.101) 0.000 0.431 

30 - 250 keV 1.244 

(0.431-1.523) 

0.590 

(0.036-0.684) 

0.695 

(0.143-0.809) 

0.536 

(0.101-0.613) 0.036 1.523 

>250 Kev 0.883 

(0.840-1.103) 

0.694 

(0.607-0.713) 

0.736 

(0.661-0.812) 

0.647 

(0.523-0.725) 0.523 1.103 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.193 

(0.008-0.474) 

0.005 

(0.000-0.039) 

0.056 

(0.001-0.157) 

0.038 

(0.001-0.111) 0.000 0.474 

30 - 250 keV 1.434 

(0.474-1.732) 

0.682 

(0.039-0.789) 

0.799 

(0.157-0.922) 

0.618 

(0.111-0.704) 0.039 1.732 

>250 Kev 1.043 

(0.973-1.284) 

0.818 

(0.704-0.841) 

0.866 

(0.772-0.940) 

0.762 

(0.606-0.839) 0.606 1.284 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 47 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Bone (Red Marrow) 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.030 

(0.016-0.063) 

0.068 

(0.030-0.154) 

0.036 

(0.015-0.084) 

0.028 

(0.012-0.066) 0.012 0.154 

30 - 250 keV 0.479 

(0.063-0.540) 

0.704 

(0.154-0.791) 

0.483 

(0.084-0.573) 

0.395 

(0.066-0.475) 0.063 0.791 

>250 keV 0.746 

(0.540-0.834) 

0.864 

(0.791-0.906) 

0.760 

(0.573-0.846) 

0.692 

(0.475-0.800) 0.475 0.906 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.030 

(0.016-0.063) 

0.069 

(0.030-0.155) 

0.036 

(0.016-0.085) 

0.028 

(0.012-0.067) 0.012 0.155 

30 - 250 keV 0.479 

(0.063-0.570) 

0.758 

(0.155-0.842) 

0.520 

(0.085-0.605) 

0.425 

(0.067-0.501) 0.063 0.842 

>250 keV 0.746 

(0.570-0.843) 

0.861 

(0.826-0.915) 

0.758 

(0.605-0.855) 

0.690 

(0.501-0.808) 0.501 0.915 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.025 

(0.004-0.063) 

0.061 

(0.008-0.155) 

0.033 

(0.004-0.085) 

0.027 

(0.003-0.067) 0.003 0.155 

30 - 250 keV 0.626 

(0.063-0.712) 

0.996 

(0.155-1.167) 

0.681 

(0.085-0.780) 

0.557 

(0.067-0.632) 0.063 1.167 

>250 keV 0.720 

(0.645-0.801) 

0.834 

(0.815-0.973) 

0.732 

(0.674-0.812) 

0.666 

(0.570-0.768) 0.570 0.973 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.028 

(0.000-0.070) 

0.067 

(0.000-0.171) 

0.036 

(0.000-0.093) 

0.028 

(0.000-0.073) 0.000 0.171 

30 - 250 keV 0.721 

(0.070-0.822) 

1.147 

(0.171-1.347) 

0.784 

(0.093-0.900) 

0.641 

(0.073-0.729) 0.070 1.347 

>250 keV 0.849 

(0.755-0.927) 

0.982 

(0.968-1.132) 

0.863 

(0.789-0.940) 

0.785 

(0.665-0.889) 0.665 1.132 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 48 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Bone (Surface) 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.215 

(0.094-0.483) 

0.283 

(0.127-0.624) 

0.224 

(0.101-0.485) 

0.170 

(0.075-0.379) 0.075 0.624 

30 - 250 keV 0.850 

(0.483-1.161) 

0.988 

(0.624-1.383) 

0.794 

(0.485-1.087) 

0.649 

(0.379-0.878) 0.379 1.383 

>250 keV 0.792 

(0.685-0.852) 

0.831 

(0.759-0.882) 

0.769 

(0.642-0.845) 

0.702 

(0.540-0.797) 0.540 0.882 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.218 

(0.095-0.488) 

0.287 

(0.129-0.631) 

0.227 

(0.102-0.490) 

0.173 

(0.076-0.384) 0.076 0.631 

30 - 250 keV 0.915 

(0.488-1.283) 

1.063 

(0.631-1.519) 

0.854 

(0.490-1.201) 

0.698 

(0.384-0.970) 0.384 1.519 

>250 keV 0.791 

(0.708-0.861) 

0.832 

(0.779-0.891) 

0.767 

(0.667-0.854) 

0.700 

(0.564-0.805) 0.564 0.891 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.209 

(0.024-0.488) 

0.278 

(0.032-0.631) 

0.217 

(0.026-0.490) 

0.162 

(0.019-0.384) 0.019 0.631 

30 - 250 keV 1.229 

(0.488-1.962) 

1.433 

(0.631-2.331) 

1.150 

(0.490-1.838) 

0.938 

(0.384-1.484) 0.384 2.331 

>250 keV 0.764 

(0.732-0.865) 

0.803 

(0.782-0.973) 

0.742 

(0.697-0.811) 

0.681 

(0.603-0.764) 0.603 0.973 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.217 

(0.001-0.537) 

0.286 

(0.002-0.694) 

0.223 

(0.002-0.539) 

0.173 

(0.001-0.422) 0.001 0.694 

30 - 250 keV 1.415 

(0.537-2.219) 

1.644 

(0.694-2.628) 

1.323 

(0.539-2.078) 

1.079 

(0.422-1.678) 0.422 2.628 

>250 keV 0.903 

(0.863-1.006) 

0.943 

(0.924-1.132) 

0.875 

(0.821-0.941) 

0.799 

(0.706-0.885) 0.706 1.132 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 49 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Breast (Female) 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.873 

(0.705-2.478) 

0.009 

(0.000-0.044) 

0.351 

(0.283-0.966) 

0.310 

(0.252-0.848) 0.000 2.478 

30 - 250 keV 0.894 

(0.862-0.918) 

0.340 

(0.044-0.452) 

0.545 

(0.404-0.604) 

0.503 

(0.380-0.563) 0.044 0.918 

>250 keV 0.966 

(0.918-0.971) 

0.763 

(0.452-0.821) 

0.798 

(0.604-0.837) 

0.768 

(0.563-0.820) 0.452 0.971 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.901 

(0.715-2.788) 

0.009 

(0.000-0.044) 

0.360 

(0.287-1.086) 

0.332 

(0.255-0.954) 0.000 2.788 

30 - 250 keV 0.960 

(0.871-0.973) 

0.366 

(0.044-0.476) 

0.587 

(0.408-0.637) 

0.540 

(0.385-0.594) 0.044 0.973 

>250 keV 0.966 

(0.947-0.969) 

0.762 

(0.476-0.828) 

0.794 

(0.637-0.845) 

0.768 

(0.594-0.828) 0.476 0.969 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.561 

(0.179-0.871) 

0.012 

(0.000-0.044) 

0.249 

(0.072-0.408) 

0.232 

(0.064-0.385) 0.000 0.871 

30 - 250 keV 1.266 

(0.871-1.488) 

0.477 

(0.044-0.554) 

0.769 

(0.408-0.852) 

0.708 

(0.385-0.776) 0.044 1.488 

>250 keV 0.930 

(0.900-1.128) 

0.735 

(0.554-0.787) 

0.769 

(0.729-0.803) 

0.741 

(0.681-0.787) 0.554 1.128 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.614 

(0.022-0.958) 

0.012 

(0.000-0.049) 

0.272 

(0.009-0.449) 

0.252 

(0.008-0.423) 0.000 0.958 

30 - 250 keV 1.460 

(0.958-1.683) 

0.549 

(0.049-0.644) 

0.884 

(0.449-0.971) 

0.815 

(0.423-0.883) 0.049 1.683 

>250 keV 1.099 

(1.042-1.313) 

0.865 

(0.644-0.911) 

0.903 

(0.851-0.930) 

0.874 

(0.794-0.911) 0.644 1.313 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 50 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Colon 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.060 

(0.000-0.226) 

0.011 

(0.000-0.059) 

0.018 

(0.000-0.085) 

0.012 

(0.000-0.056) 0.000 0.226 

30 - 250 keV 0.747 

(0.226-0.798) 

0.541 

(0.059-0.624) 

0.485 

(0.085-0.560) 

0.364 

(0.056-0.426) 0.056 0.798 

>250 keV 0.874 

(0.798-0.891) 

0.785 

(0.624-0.824) 

0.746 

(0.560-0.799) 

0.659 

(0.426-0.751) 0.426 0.891 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.061 

(0.000-0.228) 

0.011 

(0.000-0.060) 

0.019 

(0.000-0.086) 

0.012 

(0.000-0.056) 0.000 0.228 

30 - 250 keV 0.803 

(0.228-0.859) 

0.583 

(0.060-0.659) 

0.522 

(0.086-0.591) 

0.392 

(0.056-0.449) 0.056 0.859 

>250 keV 0.872 

(0.839-0.890) 

0.783 

(0.659-0.832) 

0.744 

(0.591-0.807) 

0.658 

(0.449-0.758) 0.449 0.890 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.075 

(0.000-0.228) 

0.017 

(0.000-0.060) 

0.024 

(0.000-0.086) 

0.016 

(0.000-0.056) 0.000 0.228 

30 - 250 keV 1.060 

(0.228-1.276) 

0.767 

(0.060-0.898) 

0.684 

(0.086-0.792) 

0.515 

(0.056-0.591) 0.056 1.276 

>250 keV 0.844 

(0.829-0.981) 

0.754 

(0.732-0.790) 

0.720 

(0.664-0.767) 

0.634 

(0.520-0.720) 0.520 0.981 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.081 

(0.000-0.251) 

0.014 

(0.000-0.066) 

0.025 

(0.000-0.095) 

0.015 

(0.000-0.062) 0.000 0.251 

30 - 250 keV 1.221 

(0.251-1.454) 

0.882 

(0.066-1.036) 

0.789 

(0.095-0.907) 

0.593 

(0.062-0.677) 0.062 1.454 

>250 keV 0.995 

(0.978-1.142) 

0.891 

(0.857-0.915) 

0.847 

(0.778-0.888) 

0.747 

(0.603-0.834) 0.603 1.142 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 51 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Esophagus 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.010 

(0.000-0.053) 

0.006 

(0.000-0.039) 

0.008 

(0.000-0.046) 

0.005 

(0.000-0.028) 0.000 0.053 

30 - 250 keV 0.486 

(0.053-0.573) 

0.598 

(0.039-0.688) 

0.470 

(0.046-0.552) 

0.354 

(0.028-0.426) 0.028 0.688 

>250 keV 0.772 

(0.573-0.849) 

0.813 

(0.688-0.841) 

0.778 

(0.552-0.865) 

0.678 

(0.426-0.775) 0.426 0.865 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.011 

(0.000-0.053) 

0.006 

(0.000-0.040) 

0.009 

(0.000-0.046) 

0.005 

(0.000-0.029) 0.000 0.053 

30 - 250 keV 0.523 

(0.053-0.605) 

0.644 

(0.040-0.727) 

0.506 

(0.046-0.582) 

0.381 

(0.029-0.450) 0.029 0.727 

>250 keV 0.770 

(0.605-0.857) 

0.812 

(0.724-0.845) 

0.776 

(0.582-0.874) 

0.677 

(0.450-0.783) 0.450 0.874 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.014 

(0.000-0.053) 

0.007 

(0.000-0.040) 

0.013 

(0.000-0.046) 

0.007 

(0.000-0.029) 0.000 0.053 

30 - 250 keV 0.688 

(0.053-0.803) 

0.854 

(0.040-0.986) 

0.661 

(0.046-0.767) 

0.500 

(0.029-0.576) 0.029 0.986 

>250 keV 0.745 

(0.694-0.814) 

0.782 

(0.761-0.846) 

0.743 

(0.658-0.830) 

0.654 

(0.524-0.744) 0.524 0.846 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.010 

(0.000-0.059) 

0.005 

(0.000-0.044) 

0.010 

(0.000-0.051) 

0.005 

(0.000-0.031) 0.000 0.059 

30 - 250 keV 0.792 

(0.059-0.926) 

0.975 

(0.044-1.138) 

0.764 

(0.051-0.885) 

0.575 

(0.031-0.665) 0.031 1.138 

>250 keV 0.877 

(0.809-0.943) 

0.923 

(0.897-0.984) 

0.883 

(0.766-0.961) 

0.770 

(0.607-0.861) 0.607 0.984 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 52 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Eye 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 3.624 

(1.076-33.778) 

0.000 

(0.000-0.000) 

1.477 

(0.529-12.667) 

1.199 

(0.470-9.744) 0.000 33.778 

30 - 250 keV 0.879 

(0.789-1.076) 

0.126 

(0.000-0.196) 

0.595 

(0.449-0.683) 

0.527 

(0.420-0.600) 0.000 1.076 

>250 Kev 0.908 

(0.838-0.958) 

0.573 

(0.196-0.750) 

0.854 

(0.683-0.957) 

0.788 

(0.600-0.867) 0.196 0.958 

*Upper limit should be truncated at 6.816 unless the photon energy is less than 12.5 keV 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 3.862 

(1.088-38.000) 

0.000 

(0.000-0.000) 

1.562 

(0.535-14.250) 

1.264 

(0.475-10.963) 0.000 38.000 

30 - 250 keV 0.945 

(0.850-1.088) 

0.136 

(0.000-0.206) 

0.640 

(0.472-0.721) 

0.567 

(0.435-0.633) 0.000 1.088 

>250 Kev 0.908 

(0.846-0.978) 

0.572 

(0.206-0.757) 

0.853 

(0.721-0.966) 

0.787 

(0.633-0.875) 0.206 0.978 

**Upper limit should be truncated at 7.275 unless the photon energy is less than 12.5 keV 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.936 

(0.638-1.088) 

0.000 

(0.000-0.000) 

0.437 

(0.276-0.535) 

0.383 

(0.227-0.475) 0.000 1.088 

30 - 250 keV 1.236 

(1.088-1.361) 

0.174 

(0.000-0.240) 

0.840 

(0.535-0.893) 

0.742 

(0.475-0.786) 0.000 1.361 

>250 Kev 0.880 

(0.804-1.134) 

0.549 

(0.240-0.719) 

0.825 

(0.771-0.918) 

0.759 

(0.710-0.832) 0.240 1.134 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.859 

(0.304-1.197) 

0.000 

(0.000-0.000) 

0.397 

(0.114-0.588) 

0.340 

(0.088-0.523) 0.000 1.197 

30 - 250 keV 1.421 

(1.197-1.550) 

0.201 

(0.000-0.279) 

0.966 

(0.588-1.030) 

0.854 

(0.523-0.907) 0.000 1.550 

>250 Kev 1.036 

(0.931-1.319) 

0.648 

(0.279-0.833) 

0.971 

(0.908-1.063) 

0.894 

(0.835-0.963) 0.279 1.319 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 53 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Gonads (female-ovaries) 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.034 

(0.000-0.142) 

0.013 

(0.000-0.071) 

0.012 

(0.000-0.059) 

0.005 

(0.000-0.032) 0.000 0.142 

30 - 250 keV 0.672 

(0.142-0.742) 

0.626 

(0.071-0.698) 

0.495 

(0.059-0.578) 

0.348 

(0.032-0.411) 0.032 0.742 

>250 keV 0.849 

(0.742-0.950) 

0.803 

(0.698-0.833) 

0.759 

(0.578-0.869) 

0.651 

(0.411-0.752) 0.411 0.950 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.031 

(0.000-0.144) 

0.014 

(0.000-0.071) 

0.012 

(0.000-0.060) 

0.005 

(0.000-0.032) 0.000 0.144 

30 - 250 keV 0.726 

(0.144-0.795) 

0.674 

(0.071-0.749) 

0.532 

(0.060-0.610) 

0.375 

(0.032-0.434) 0.032 0.795 

>250 keV 0.848 

(0.771-0.960) 

0.800 

(0.735-0.842) 

0.758 

(0.610-0.878) 

0.650 

(0.434-0.760) 0.434 0.960 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.047 

(0.000-0.144) 

0.019 

(0.000-0.071) 

0.022 

(0.000-0.060) 

0.009 

(0.000-0.032) 0.000 0.144 

30 - 250 keV 0.955 

(0.144-1.111) 

0.888 

(0.071-1.069) 

0.702 

(0.060-0.803) 

0.494 

(0.032-0.577) 0.032 1.111 

>250 keV 0.819 

(0.782-0.913) 

0.775 

(0.762-0.858) 

0.732 

(0.668-0.834) 

0.626 

(0.505-0.722) 0.505 0.913 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.030 

(0.000-0.158) 

0.015 

(0.000-0.079) 

0.012 

(0.000-0.066) 

0.007 

(0.000-0.035) 0.000 0.158 

30 - 250 keV 1.102 

(0.158-1.282) 

1.022 

(0.079-1.234) 

0.805 

(0.066-0.926) 

0.566 

(0.035-0.666) 0.035 1.282 

>250 keV 0.966 

(0.918-1.062) 

0.913 

(0.905-0.999) 

0.862 

(0.786-0.966) 

0.736 

(0.586-0.836) 0.586 1.062 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 54 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Gonads (male-testes) 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.978 

(0.739-3.244) 

0.008 

(0.000-0.037) 

0.278 

(0.216-0.827) 

0.235 

(0.169-0.621) 0.000 3.244 

30 - 250 keV 1.011 

(0.983-1.026) 

0.350 

(0.037-0.461) 

0.519 

(0.343-0.568) 

0.451 

(0.303-0.501) 0.037 1.026 

>250 keV 0.973 

(0.904-1.010) 

0.737 

(0.461-0.796) 

0.763 

(0.568-0.846) 

0.720 

(0.501-0.804) 0.461 1.010 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.918 

(0.750-3.650) 

0.008 

(0.000-0.037) 

0.277 

(0.220-0.930) 

0.246 

(0.172-0.699) 0.000 3.650 

30 - 250 keV 1.090 

(0.994-1.135) 

0.376 

(0.037-0.487) 

0.557 

(0.346-0.600) 

0.483 

(0.306-0.528) 0.037 1.135 

>250 keV 0.974 

(0.913-1.056) 

0.734 

(0.487-0.804) 

0.758 

(0.600-0.855) 

0.715 

(0.528-0.812) 0.487 1.056 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.622 

(0.188-0.994) 

0.011 

(0.000-0.037) 

0.204 

(0.055-0.346) 

0.179 

(0.043-0.306) 0.000 0.994 

30 - 250 keV 1.434 

(0.994-1.734) 

0.491 

(0.037-0.566) 

0.732 

(0.346-0.831) 

0.632 

(0.306-0.715) 0.037 1.734 

>250 keV 0.941 

(0.867-1.231) 

0.709 

(0.566-0.763) 

0.735 

(0.665-0.812) 

0.693 

(0.612-0.771) 0.566 1.231 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.516 

(0.029-1.093) 

0.008 

(0.000-0.041) 

0.169 

(0.007-0.381) 

0.144 

(0.006-0.337) 0.000 1.093 

30 - 250 keV 1.649 

(1.093-1.961) 

0.564 

(0.041-0.658) 

0.843 

(0.381-0.946) 

0.729 

(0.337-0.815) 0.041 1.961 

>250 keV 1.108 

(1.004-1.432) 

0.835 

(0.658-0.884) 

0.866 

(0.779-0.940) 

0.818 

(0.710-0.893) 0.658 1.432 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 55 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Liver 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.095 

(0.000-0.286) 

0.039 

(0.000-0.143) 

0.042 

(0.000-0.143) 

0.027 

(0.000-0.098) 0.000 0.286 

30 - 250 keV 0.748 

(0.286-0.794) 

0.576 

(0.143-0.645) 

0.516 

(0.143-0.578) 

0.402 

(0.098-0.462) 0.098 0.794 

>250 keV 0.886 

(0.794-0.904) 

0.807 

(0.645-0.843) 

0.766 

(0.578-0.818) 

0.691 

(0.462-0.753) 0.462 0.904 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.092 

(0.000-0.289) 

0.040 

(0.000-0.145) 

0.042 

(0.000-0.145) 

0.028 

(0.000-0.099) 0.000 0.289 

30 - 250 keV 0.805 

(0.289-0.850) 

0.620 

(0.145-0.680) 

0.556 

(0.145-0.610) 

0.432 

(0.099-0.488) 0.099 0.850 

>250 keV 0.884 

(0.835-0.904) 

0.805 

(0.680-0.848) 

0.764 

(0.610-0.826) 

0.690 

(0.488-0.761) 0.488 0.904 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.106 

(0.003-0.289) 

0.048 

(0.001-0.145) 

0.050 

(0.001-0.145) 

0.033 

(0.000-0.099) 0.000 0.289 

30 - 250 keV 1.064 

(0.289-1.269) 

0.816 

(0.145-0.951) 

0.731 

(0.145-0.852) 

0.568 

(0.099-0.653) 0.099 1.269 

>250 keV 0.845 

(0.844-0.976) 

0.780 

(0.749-0.806) 

0.740 

(0.680-0.785) 

0.665 

(0.564-0.723) 0.564 0.976 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.086 

(0.000-0.318) 

0.037 

(0.000-0.159) 

0.039 

(0.000-0.159) 

0.027 

(0.000-0.109) 0.000 0.318 

30 - 250 keV 1.221 

(0.318-1.446) 

0.938 

(0.159-1.083) 

0.841 

(0.159-0.970) 

0.654 

(0.109-0.744) 0.109 1.446 

>250 keV 1.007 

(0.994-1.135) 

0.917 

(0.881-0.935) 

0.870 

(0.795-0.909) 

0.784 

(0.654-0.837) 0.654 1.135 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 56 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Lung 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.082 

(0.000-0.267) 

0.109 

(0.000-0.324) 

0.052 

(0.000-0.180) 

0.035 

(0.000-0.127) 0.000 0.324 

30 - 250 keV 0.695 

(0.267-0.750) 

0.754 

(0.324-0.813) 

0.552 

(0.180-0.615) 

0.441 

(0.127-0.503) 0.127 0.813 

>250 keV 0.870 

(0.750-0.884) 

0.909 

(0.813-0.917) 

0.802 

(0.615-0.845) 

0.730 

(0.503-0.804) 0.503 0.917 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.083 

(0.000-0.270) 

0.109 

(0.000-0.327) 

0.053 

(0.000-0.182) 

0.035 

(0.000-0.128) 0.000 0.327 

30 - 250 keV 0.749 

(0.270-0.792) 

0.812 

(0.327-0.858) 

0.595 

(0.182-0.649) 

0.475 

(0.128-0.531) 0.128 0.858 

>250 keV 0.866 

(0.792-0.883) 

0.906 

(0.858-0.914) 

0.801 

(0.649-0.854) 

0.727 

(0.531-0.812) 0.531 0.914 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.100 

(0.002-0.270) 

0.120 

(0.003-0.327) 

0.055 

(0.001-0.182) 

0.042 

(0.001-0.128) 0.001 0.327 

30 - 250 keV 0.986 

(0.270-1.168) 

1.077 

(0.327-1.260) 

0.779 

(0.182-0.912) 

0.625 

(0.128-0.717) 0.128 1.260 

>250 keV 0.842 

(0.834-0.922) 

0.875 

(0.860-1.000) 

0.773 

(0.732-0.811) 

0.706 

(0.614-0.771) 0.614 1.000 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.076 

(0.000-0.297) 

0.098 

(0.000-0.360) 

0.049 

(0.000-0.200) 

0.033 

(0.000-0.141) 0.000 0.360 

30 - 250 keV 1.133 

(0.297-1.331) 

1.230 

(0.360-1.435) 

0.899 

(0.200-1.039) 

0.718 

(0.141-0.817) 0.141 1.435 

>250 keV 0.989 

(0.971-1.073) 

1.034 

(0.999-1.163) 

0.911 

(0.856-0.939) 

0.828 

(0.712-0.893) 0.712 1.163 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 57 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Remainder Organs 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.078 

(0.024-0.192) 

0.080 

(0.024-0.191) 

0.052 

(0.017-0.131) 

0.036 

(0.012-0.094) 0.012 0.192 

30 - 250 keV 0.621 

(0.192-0.681) 

0.623 

(0.191-0.688) 

0.498 

(0.131-0.569) 

0.393 

(0.094-0.459) 0.094 0.688 

>250 keV 0.815 

(0.681-0.841) 

0.818 

(0.688-0.853) 

0.761 

(0.569-0.824) 

0.689 

(0.459-0.770) 0.459 0.853 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.079 

(0.025-0.195) 

0.081 

(0.025-0.193) 

0.052 

(0.017-0.133) 

0.036 

(0.012-0.095) 0.012 0.195 

30 - 250 keV 0.668 

(0.195-0.719) 

0.670 

(0.193-0.726) 

0.536 

(0.133-0.600) 

0.423 

(0.095-0.484) 0.095 0.726 

>250 keV 0.814 

(0.719-0.847) 

0.815 

(0.726-0.862) 

0.759 

(0.600-0.833) 

0.686 

(0.484-0.777) 0.484 0.862 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.071 

(0.006-0.195) 

0.075 

(0.006-0.193) 

0.050 

(0.004-0.133) 

0.035 

(0.003-0.095) 0.003 0.195 

30 - 250 keV 0.879 

(0.195-1.033) 

0.885 

(0.193-1.033) 

0.705 

(0.133-0.808) 

0.555 

(0.095-0.629) 0.095 1.033 

>250 keV 0.787 

(0.773-0.837) 

0.793 

(0.775-0.846) 

0.735 

(0.678-0.791) 

0.663 

(0.561-0.738) 0.561 0.846 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.060 

(0.001-0.214) 

0.061 

(0.001-0.212) 

0.040 

(0.000-0.146) 

0.028 

(0.000-0.104) 0.000 0.214 

30 - 250 keV 1.014 

(0.214-1.177) 

1.017 

(0.212-1.177) 

0.812 

(0.146-0.925) 

0.639 

(0.104-0.719) 0.104 1.177 

>250 keV 0.927 

(0.911-0.974) 

0.929 

(0.913-0.984) 

0.864 

(0.794-0.916) 

0.781 

(0.650-0.855) 0.650 0.984 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 58 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ:Skin 

Photon Exposures 

Deep Dose Equivalent (Hp(10)) to Organ Dose (HT) 

If Hp(10) was measured the shallow dose equivalent Hp(0.07) should also be available and should be used for skin dose. 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 1.839 

(0.595-29.375) 

1.798 

(0.589-29.625) 

1.580 

(0.528-25.000) 

1.989 

(0.495-21.500) 0.495 3.785* 

30 - 250 keV 0.677 

(0.550-0.744) 

0.674 

(0.541-0.741) 

0.608 

(0.486-0.676) 

0.564 

(0.448-0.622) 0.448 0.744 

>250 keV 0.863 

(0.744-0.893) 

0.860 

(0.741-0.902) 

0.822 

(0.676-0.864) 

0.787 

(0.622-0.835) 0.622 0.902 

*Upper level truncated at 12.5 keV (midpoint between last two data points). If photon energy is less than 12.5 kev, the data in this 

The data in this table cannot be used. 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.504 

(0.363-0.595) 

0.502 

(0.363-0.589) 

0.447 

(0.318-0.528) 

0.418 

(0.291-0.495) 0.291 0.595 

30 - 250 keV 0.892 

(0.595-0.974) 

0.885 

(0.589-0.962) 

0.799 

(0.528-0.861) 

0.731 

(0.495-0.778) 0.495 0.974 

>250 keV 0.835 

(0.823-0.866) 

0.837 

(0.821-0.863) 

0.796 

(0.768-0.820) 

0.759 

(0.711-0.793) 0.711 0.866 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.473 

(0.235-0.654) 

0.470 

(0.237-0.648) 

0.418 

(0.200-0.581) 

0.388 

(0.172-0.544) 0.172 0.654 

30 - 250 keV 1.027 

(0.654-1.109) 

1.019 

(0.648-1.096) 

0.920 

(0.581-0.981) 

0.841 

(0.544-0.886) 0.544 1.109 

>250 keV 0.986 

(0.970-1.007) 

0.987 

(0.966-1.004) 

0.941 

(0.899-0.953) 

0.895 

(0.832-0.919) 0.832 1.007 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 59 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Stomach 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.167 

(0.001-0.434) 

0.008 

(0.000-0.044) 

0.052 

(0.000-0.152) 

0.034 

(0.000-0.110) 0.000 0.434 

30 - 250 keV 0.881 

(0.434-0.914) 

0.437 

(0.044-0.520) 

0.513 

(0.152-0.576) 

0.401 

(0.110-0.459) 0.044 0.914 

>250 Kev 0.915 

(0.902-0.919) 

0.736 

(0.520-0.795) 

0.775 

(0.576-0.841) 

0.690 

(0.459-0.763) 0.459 0.919 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.167 

(0.001-0.439) 

0.008 

(0.000-0.044) 

0.053 

(0.000-0.154) 

0.035 

(0.000-0.111) 0.000 0.439 

30 - 250 keV 0.950 

(0.439-1.012) 

0.470 

(0.044-0.548) 

0.551 

(0.154-0.607) 

0.431 

(0.111-0.484) 0.044 1.012 

>250 keV 0.916 

(0.908-0.958) 

0.735 

(0.548-0.803) 

0.773 

(0.607-0.849) 

0.690 

(0.484-0.771) 0.484 0.958 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.182 

(0.008-0.439) 

0.011 

(0.000-0.044) 

0.058 

(0.002-0.154) 

0.040 

(0.001-0.111) 0.000 0.439 

30 - 250 keV 1.251 

(0.439-1.534) 

0.618 

(0.044-0.706) 

0.725 

(0.154-0.853) 

0.566 

(0.111-0.648) 0.044 1.534 

>250 keV 0.885 

(0.863-1.117) 

0.710 

(0.637-0.763) 

0.747 

(0.685-0.807) 

0.664 

(0.556-0.732) 0.556 1.117 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.143 

(0.000-0.483) 

0.008 

(0.000-0.049) 

0.046 

(0.000-0.169) 

0.032 

(0.000-0.122) 0.000 0.483 

30 - 250 keV 1.441 

(0.483-1.740) 

0.710 

(0.049-0.815) 

0.838 

(0.169-0.972) 

0.652 

(0.122-0.739) 0.049 1.740 

>250 keV 1.044 

(1.002-1.299) 

0.836 

(0.738-0.883) 

0.879 

(0.803-0.934) 

0.783 

(0.644-0.848) 0.644 1.299 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 60 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Thymus 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.273 

(0.000-0.629) 

0.000 

(0.000-0.007) 

0.077 

(0.000-0.201) 

0.051 

(0.000-0.143) 0.000 0.629 

30 - 250 keV 0.991 

(0.629-1.030) 

0.273 

(0.007-0.345) 

0.528 

(0.201-0.598) 

0.434 

(0.143-0.498) 0.007 1.030 

>250 keV 0.922 

(0.840-0.999) 

0.593 

(0.345-0.732) 

0.764 

(0.598-0.839) 

0.708 

(0.498-0.788) 0.345 0.999 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.274 

(0.000-0.636) 

0.000 

(0.000-0.007) 

0.077 

(0.000-0.204) 

0.051 

(0.000-0.145) 0.000 0.636 

30 - 250 keV 1.065 

(0.636-1.131) 

0.292 

(0.007-0.364) 

0.568 

(0.204-0.631) 

0.467 

(0.145-0.525) 0.007 1.131 

>250 keV 0.922 

(0.848-1.054) 

0.590 

(0.364-0.739) 

0.763 

(0.631-0.847) 

0.707 

(0.525-0.795) 0.364 1.054 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.288 

(0.015-0.636) 

0.000 

(0.000-0.007) 

0.083 

(0.003-0.204) 

0.057 

(0.002-0.145) 0.000 0.636 

30 - 250 keV 1.408 

(0.636-1.692) 

0.381 

(0.007-0.441) 

0.746 

(0.204-0.846) 

0.614 

(0.145-0.692) 0.007 1.692 

>250 keV 0.892 

(0.806-1.229) 

0.566 

(0.422-0.702) 

0.737 

(0.705-0.805) 

0.682 

(0.606-0.756) 0.422 1.229 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.226 

(0.000-0.700) 

0.001 

(0.000-0.008) 

0.067 

(0.000-0.224) 

0.045 

(0.000-0.159) 0.000 0.700 

30 - 250 keV 1.620 

(0.700-1.926) 

0.444 

(0.008-0.505) 

0.859 

(0.224-0.974) 

0.706 

(0.159-0.788) 0.008 1.926 

>250 keV 1.052 

(0.933-1.429) 

0.672 

(0.489-0.813) 

0.868 

(0.831-0.932) 

0.804 

(0.703-0.875) 0.489 1.429 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 61 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Thyroid 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.538 

(0.140-0.818) 

0.000 

(0.000-0.010) 

0.193 

(0.032-0.368) 

0.087 

(0.013-0.185) 0.000 0.818 

30 - 250 keV 1.017 

(0.818-1.042) 

0.298 

(0.010-0.385) 

0.684 

(0.368-0.757) 

0.453 

(0.185-0.522) 0.010 1.042 

>250 keV 1.003 

(0.906-1.066) 

0.684 

(0.385-0.809) 

0.927 

(0.757-0.961) 

0.740 

(0.522-0.842) 0.385 1.066 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.545 

(0.158-0.827) 

0.000 

(0.000-0.010) 

0.192 

(0.036-0.372) 

0.089 

(0.015-0.187) 0.000 0.827 

30 - 250 keV 1.091 

(0.827-1.135) 

0.321 

(0.010-0.406) 

0.735 

(0.372-0.799) 

0.487 

(0.187-0.551) 0.010 1.135 

>250 keV 1.004 

(0.915-1.089) 

0.683 

(0.406-0.817) 

0.925 

(0.799-0.967) 

0.739 

(0.551-0.850) 0.406 1.089 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.473 

(0.093-0.827) 

0.003 

(0.000-0.010) 

0.183 

(0.022-0.372) 

0.087 

(0.009-0.187) 0.000 0.827 

30 - 250 keV 1.440 

(0.827-1.702) 

0.420 

(0.010-0.475) 

0.965 

(0.372-1.083) 

0.639 

(0.187-0.718) 0.010 1.702 

>250 keV 0.972 

(0.870-1.269) 

0.663 

(0.472-0.776) 

0.894 

(0.868-0.930) 

0.714 

(0.637-0.808) 0.472 1.269 

Kerma (Ka) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.377 

(0.001-0.910) 

0.001 

(0.000-0.011) 

0.146 

(0.000-0.409) 

0.068 

(0.000-0.206) 0.000 0.910 

30 - 250 keV 1.660 

(0.910-1.938) 

0.483 

(0.011-0.549) 

1.112 

(0.409-1.234) 

0.735 

(0.206-0.818) 0.011 1.938 

>250 keV 1.143 

(1.007-1.477) 

0.777 

(0.549-0.899) 

1.054 

(1.019-1.082) 

0.841 

(0.739-0.935) 0.549 1.477 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 62 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Uterus 

Photon Exposures 

Personal Dose Equivalent (Hp(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.044 

(0.000-0.195) 

0.012 

(0.000-0.063) 

0.013 

(0.000-0.068) 

0.009 

(0.000-0.044) 0.000 0.195 

30 - 250 keV 0.711 

(0.195-0.762) 

0.546 

(0.063-0.621) 

0.461 

(0.068-0.530) 

0.343 

(0.044-0.402) 0.044 0.762 

>250 keV 0.812 

(0.754-0.820) 

0.757 

(0.621-0.782) 

0.713 

(0.530-0.778) 

0.628 

(0.402-0.729) 0.402 0.820 

Ambient Dose Equivalent (H*(10)) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.045 

(0.000-0.197) 

0.013 

(0.000-0.064) 

0.015 

(0.000-0.069) 

0.009 

(0.000-0.045) 0.000 0.197 

30 - 250 keV 0.765 

(0.197-0.834) 

0.588 

(0.064-0.656) 

0.497 

(0.069-0.559) 

0.369 

(0.045-0.424) 0.045 0.834 

>250 keV 0.811 

(0.784-0.817) 

0.758 

(0.656-0.781) 

0.711 

(0.559-0.785) 

0.627 

(0.424-0.736) 0.424 0.817 

Exposure (R) to Organ Dose (HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.061 

(0.000-0.197) 

0.017 

(0.000-0.064) 

0.019 

(0.000-0.069) 

0.012 

(0.000-0.045) 0.000 0.197 

30 - 250 keV 1.011 

(0.197-1.212) 

0.774 

(0.064-0.913) 

0.653 

(0.069-0.757) 

0.485 

(0.045-0.553) 0.045 1.212 

>250 keV 0.786 

(0.764-0.928) 

0.734 

(0.724-0.764) 

0.688 

(0.633-0.746) 

0.604 

(0.485-0.700) 0.485 0.928 

Kerma (Ka) to Organ Dose 

(HT) 

Photon Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<30 keV 0.045 

(0.000-0.217) 

0.010 

(0.000-0.070) 

0.014 

(0.000-0.076) 

0.009 

(0.000-0.049) 0.000 0.217 

30 - 250 keV 1.163 

(0.217-1.381) 

0.890 

(0.070-1.054) 

0.751 

(0.076-0.874) 

0.558 

(0.049-0.636) 0.049 1.381 

>250 keV 0.924 

(0.885-1.079) 

0.863 

(0.853-0.888) 

0.809 

(0.739-0.864) 

0.712 

(0.562-0.810) 0.562 1.079 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 63 of 77 

November 21, 2007 3 OCAS-IG-001 

APPENDIX A – NEUTRON DOSE CONVERSION FACTORS (DCF) 

Organ: Bladder 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 2.214E-09 

(6.40E-10 - 2.51E-9) 

9.388E-10 

(2.50E-10 - 1.08E-9) 

9.704E-10 

(2.75E-10 - 1.11E-9) 

6.945E-10 

(2.30E-10 - 7.97E-10) 2.30E-10 2.51E-09 

10 - 100 keV 5.175E-09 

(2.51E-9 - 7.23E-9) 

2.133E-09 

(1.08E-9 - 3.05E-9) 

2.286E-09 

(1.11E-9 - 3.29E-9) 

1.779E-09 

(7.97E-10 - 2.57E-9) 7.97E-10 7.23E-09 

0.1 - 2.0 Mev 3.119E-08 

(7.23E-9 - 4.47E-8) 

8.458E-09 

(3.05E-9 - 1.42E-8) 

1.273E-08 

(3.29E-9 - 1.98E-8) 

9.070E-09 

(2.57E-9 - 1.46E-8) 2.57E-09 4.47E-08 

2.0 - 20.0 Mev 5.462E-08 

(4.47E-8 - 5.64E-8) 

3.377E-08 

(1.42E-8 - 4.00E-8) 

3.502E-08 

(1.98E-8 - 3.96E-8) 

2.853E-08 

(1.46E-8 - 3.25E-8) 1.42E-08 5.64E-08 

> 20.0 Mev 4.607E-08 

(4.20E-8 - 5.32E-8) 

5.276E-08 

(4.00E-8 - 6.97E-8) 

4.925E-08 

(3.96E-8 - 5.91E-8) 

n/a 

3.96E-08 6.97E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 2.633 

(0.906-2.755) 

1.114 

(0.361-1.161) 

1.153 

(0.372-1.195) 

0.826 

(0.311-0.852) 0.311 2.755 

10 - 100 keV 1.291 

(0.822-2.392) 

0.558 

(0.346-1.030) 

0.575 

(0.374-1.060) 

0.438 

(0.292-0.759) 0.292 2.392 

0.1 - 2.0 Mev 0.822 

(0.661-1.065) 

0.229 

(0.168-0.346) 

0.333 

(0.258-0.471) 

0.243 

(0.184-0.348) 0.168 1.065 

2.0 - 20.0 Mev 1.170 

(0.887-1.401) 

0.708 

(0.338-0.813) 

0.740 

(0.471-0.850) 

0.601 

(0.348-0.685) 0.338 1.401 

> 20.0 Mev 1.488 

(0.887-1.767) 

1.790 

(0.666-2.789) 

1.653 

(0.660-2.365) 

n/a 

0.660 2.789 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 2.301 

(0.781-2.355) 

0.974 

(0.305-0.992) 

1.007 

(0.336-1.022) 

0.720 

(0.281-0.733) 0.281 2.355 

10 - 100 keV 1.268 

(0.798-2.243) 

0.549 

(0.336-0.966) 

0.570 

(0.363-0.994) 

0.432 

(0.283-0.712) 0.283 2.243 

0.1 - 2.0 Mev 0.796 

(0.626-1.012) 

0.216 

(0.163-0.336) 

0.326 

(0.247-0.447) 

0.234 

(0.177-0.331) 0.163 1.012 

2.0 - 20.0 Mev 1.105 

(0.887-1.325) 

0.670 

(0.321-0.740) 

0.698 

(0.447-0.780) 

0.568 

(0.331-0.629) 0.321 1.325 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 64 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Bone (Red Marrow) 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 9.868E-10

(3.05E-10 - 1.15E-9) 

1.568E-09

(5.70E-10 - 1.82E-9) 

9.450E-10

(3.10E-10 - 1.10E-9) 

6.618E-10

(2.40E-10 - 7.66E-10) 2.40E-10 1.82E-09

10 - 100 keV 2.676E-09

(1.15E-9 - 3.95E-9) 

4.282E-09

(1.82E-9 - 6.46E-9) 

2.506E-09

(1.10E-9 - 3.72E-9) 

1.914E-09

(7.66E-10 - 2.86E-9) 7.66E-10 6.46E-09

0.1 - 2.0 Mev 1.415E-08

(3.95E-9 - 2.22E-8) 

2.709E-08

(6.46E-9 - 3.90E-8) 

1.600E-08

(3.72E-9 - 2.41E-8) 

1.200E-08

(2.86E-9 - 1.79E-8) 2.86E-09 3.90E-08

2.0 - 20.0 Mev 3.587E-08

(2.22E-8 - 3.83E-8)

4.567E-08

(3.90E-8 - 4.73E-8) 

3.504E-08

(2.41E-8 - 3.66E-8) 

2.897E-08

(1.79E-8 - 3.28E-8) 1.79E-08 4.73E-08

> 20.0 Mev 4.183E-08

(3.74E-8 - 4.86E-8) 

4.025E-08

(3.89E-8 - 4.40E-8) 

3.999E-08

(3.59E-8 - 4.66E-8) 

n/a 

3.59E-08 4.86E-08

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.167 

(0.422-1.209) 

1.861 

(0.759-1.930) 

1.113 

(0.443-1.161) 

0.786 

(0.335-0.811) 0.335 1.930 

10 - 100 keV 0.659 

(0.448-1.091) 

1.042 

(0.735-1.729) 

0.615 

(0.423-1.048) 

0.455 

(0.324-0.729) 0.324 1.729 

0.1 - 2.0 Mev 0.375 

(0.279-0.528) 

0.716 

(0.585-0.929) 

0.422 

(0.336-0.574) 

0.316 

(0.253-0.425) 0.253 0.929 

2.0 - 20.0 Mev 0.761 

(0.528-0.891) 

0.980 

(0.733-1.179) 

0.745 

(0.574-0.872) 

0.611 

(0.425-0.682) 0.425 1.179 

> 20.0 Mev 1.395 

(0.633-1.942) 

1.320 

(0.733-1.700) 

1.334 

(0.606-1.863) 

n/a 

0.606 1.942 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.023 

(0.372-1.033) 

1.635 

(0.696-1.650) 

0.980 

(0.379-0.992) 

0.688 

(0.293-0.693) 0.293 1.650 

10 - 100 keV 0.651 

(0.436-1.022) 

1.028 

(0.713-1.621) 

0.607 

(0.411-0.983) 

0.452 

(0.315-0.683) 0.315 1.621 

0.1 - 2.0 Mev 0.361 

(0.268-0.502) 

0.690 

(0.554-0.883) 

0.407 

(0.318-0.545) 

0.305 

(0.240-0.404) 0.240 0.883 

2.0 - 20.0 Mev 0.720 

(0.502-0.825) 

0.927 

(0.733-1.125) 

0.705 

(0.545-0.814) 

0.578 

(0.404-0.629) 0.404 1.125 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 65 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Bone (Surface) 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.045E-09 

(3.85E-10 - 1.21E-9) 

1.245E-09 

(4.70E-10 - 1.43E-9) 

8.755E-10 

(3.35E-10 - 1.02E-9) 

6.340E-10 

(2.70E-10 - 7.47E-10) 2.70E-10 1.43E-09 

10 - 100 keV 2.671E-09 

(1.21E-9 - 4.03E-9) 

3.354E-09 

(1.43E-9 - 5.07E-9) 

2.400E-09 

(1.02E-9 - 3.66E-9) 

1.834E-09 

(7.47E-10 - 2.81E-9) 7.47E-10 5.07E-09 

0.1 - 2.0 Mev 1.696E-08 

(4.03E-9 - 2.41E-8) 

2.056E-08 

(5.07E-9 - 2.88E-8) 

1.633E-08 

(3.66E-9 - 2.34E-8) 

1.301E-08 

(2.81E-9 - 1.87E-8) 2.81E-09 2.88E-08 

2.0 - 20.0 Mev 3.364E-08 

(2.41E-8 - 3.62E-8) 

3.688E-08 

(2.88E-8 - 3.85E-8) 

3.214E-08 

(2.34E-8 - 3.41E-8) 

2.765E-08 

(1.87E-8 - 3.08E-8) 1.87E-08 3.85E-08 

> 20.0 Mev 4.179E-08 

(3.62E-8 - 4.84E-8) 

3.990E-08 

(3.82E-8 - 4.21E-8) 

3.996E-08 

(3.41E-8 - 4.62E-8) 

n/a 

3.41E-08 4.84E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.239 

(0.519-1.292) 

1.479 

(0.632-1.525) 

1.038 

(0.472-1.072) 

0.752 

(0.340-0.776) 0.340 1.525 

10 - 100 keV 0.666 

(0.457-1.151) 

0.817 

(0.576-1.362) 

0.586 

(0.416-0.970) 

0.441 

(0.319-0.711) 0.319 1.362 

0.1 - 2.0 Mev 0.451 

(0.373-0.574) 

0.547 

(0.455-0.685) 

0.433 

(0.351-0.557) 

0.343 

(0.273-0.446) 0.273 0.685 

2.0 - 20.0 Mev 0.714 

(0.574-0.818) 

0.785 

(0.641-0.903) 

0.682 

(0.557-0.787) 

0.586 

(0.446-0.680) 0.446 0.903 

> 20.0 Mev 1.394 

(0.603-1.934) 

1.315 

(0.641-1.686) 

1.335 

(0.569-1.849) 

n/a 

0.569 1.934 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.083 

(0.470-1.104) 

1.292 

(0.574-1.312) 

0.908 

(0.409-0.916) 

0.657 

(0.311-0.667) 0.311 1.312 

10 - 100 keV 0.656 

(0.444-1.079) 

0.807 

(0.559-1.277) 

0.577 

(0.404-0.909) 

0.435 

(0.310-0.667) 0.310 1.277 

0.1 - 2.0 Mev 0.436 

(0.353-0.545) 

0.529 

(0.433-0.651) 

0.417 

(0.332-0.530) 

0.332 

(0.259-0.424) 0.259 0.651 

2.0 - 20.0 Mev 0.675 

(0.545-0.758) 

0.743 

(0.641-0.848) 

0.646 

(0.530-0.731) 

0.554 

(0.424-0.629) 0.424 0.848 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 66 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Breast (Female) 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.366E-09 

(8.40E-10 - 1.66E-9) 

4.783E-10 

(1.40E-10 - 5.50E-10) 

6.798E-10 

(3.45E-10 - 8.22E-10) 

5.023E-10 

(2.95E-10 - 6.14E-10) 1.40E-10 1.66E-09 

10 - 100 keV 4.905E-09 

(1.66E-9 - 8.28E-9) 

1.073E-09 

(5.50E-10 - 1.52E-9) 

2.362E-09 

(8.22E-10 - 3.85E-9) 

2.099E-09 

(6.14E-10 - 3.66E-9) 5.50E-10 8.28E-09 

0.1 - 2.0 Mev 4.469E-08 

(8.28E-9 - 5.71E-8) 

6.863E-09 

(1.52E-9 - 1.34E-8) 

2.323E-08 

(3.85E-9 - 3.09E-8) 

2.143E-08 

(3.66E-9 - 3.00E-8) 1.52E-09 5.71E-08 

2.0 - 20.0 Mev 5.514E-08 

(5.08E-8 - 5.77E-8) 

3.134E-08 

(1.34E-8 - 3.73E-8) 

3.619E-08 

(3.09E-8 - 3.81E-8) 

3.668E-08 

(3.00E-8 - 3.93E-8) 1.34E-08 5.77E-08 

> 20.0 Mev 3.153E-08 

(2.48E-8 - 5.08E-8) 

4.586E-08 

(3.73E-8 - 5.31E-8) 

2.902E-08 

(2.73E-8 - 3.64E-8) 

n/a 

2.48E-08 5.31E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.612 

(0.938-1.676) 

0.569 

(0.172-0.591) 

0.803 

(0.419-0.838) 

0.595 

(0.333-0.611) 0.172 1.676 

10 - 100 keV 1.117 

(0.941-1.585) 

0.276 

(0.173-0.524) 

0.548 

(0.437-0.783) 

0.472 

(0.416-0.584) 0.173 1.585 

0.1 - 2.0 Mev 1.180 

(0.940-1.358) 

0.180 

(0.106-0.318) 

0.611 

(0.437-0.735) 

0.563 

(0.414-0.714) 0.106 1.358 

2.0 - 20.0 Mev 1.185 

(0.846-1.412) 

0.657 

(0.318-0.758) 

0.789 

(0.607-0.884) 

0.779 

(0.642-0.878) 0.318 1.412 

> 20.0 Mev 0.982 

(0.846-1.050) 

1.534 

(0.622-2.122) 

0.928 

(0.607-1.223) 

n/a 

0.607 2.122 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.411 

(0.925-1.486) 

0.498 

(0.155-0.505) 

0.709 

(0.408-0.734) 

0.525 

(0.320-0.548) 0.155 1.486 

10 - 100 keV 1.111 

(0.914-1.486) 

0.271 

(0.168-0.491) 

0.545 

(0.425-0.734) 

0.471 

(0.404-0.548) 0.168 1.486 

0.1 - 2.0 Mev 1.145 

(0.892-1.291) 

0.173 

(0.101-0.302) 

0.592 

(0.420-0.698) 

0.542 

(0.393-0.679) 0.101 1.291 

2.0 - 20.0 Mev 1.121 

(0.846-1.355) 

0.622 

(0.302-0.690) 

0.729 

(0.607-0.817) 

0.737 

(0.642-0.839) 0.302 1.355 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 67 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Colon 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.697E-09 

(4.45E-10 - 1.94E-9) 

1.264E-09 

(3.85E-10 - 1.46E-9) 

9.216E-10 

(2.65E-10 - 1.05E-9) 

7.074E-10 

(2.00E-10 - 8.10E-10) 2.00E-10 1.94E-09 

10 - 100 keV 3.688E-09 

(1.94E-9 - 5.13E-9) 

2.988E-09 

(1.46E-9 - 4.28E-9) 

2.297E-09 

(1.05E-9 - 3.10E-9) 

1.717E-09 

(8.10E-10 - 2.44E-9) 8.10E-10 5.13E-09 

0.1 - 2.0 Mev 1.926E-08 

(5.13E-9 - 3.02E-8) 

1.324E-08 

(4.28E-9 - 2.18E-8) 

1.086E-08 

(3.10E-9 - 1.80E-8) 

7.476E-09 

(2.44E-9 - 1.24E-8) 2.44E-09 3.02E-08 

2.0 - 20.0 Mev 4.539E-08 

(3.02E-8 - 4.78E-8) 

3.879E-08 

(2.18E-8 - 4.44E-8) 

3.307E-08 

(1.80E-8 - 3.79E-8) 

2.723E-08 

(1.24E-8 - 3.25E-8) 1.24E-08 4.78E-08 

> 20.0 Mev 4.888E-08 

(4.78E-8 - 4.94E-8) 

5.055E-08 

(4.44E-8 - 5.36E-8) 

4.593E-08 

(3.79E-8 - 5.66E-8) 

n/a 

3.79E-08 5.66E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 2.012 

(0.589-2.102) 

1.500 

(0.533-1.559) 

1.090 

(0.367-1.134) 

0.837 

(0.278-0.872) 0.278 2.102 

10 - 100 keV 0.961 

(0.583-1.850) 

0.767 

(0.487-1.386) 

0.554 

(0.352-1.000) 

0.431 

(0.277-0.771) 0.277 1.850 

0.1 - 2.0 Mev 0.504 

(0.375-0.718) 

0.355 

(0.262-0.520) 

0.283 

(0.208-0.429) 

0.200 

(0.152-0.295) 0.152 0.718 

2.0 - 20.0 Mev 0.967 

(0.718-1.127) 

0.818 

(0.520-0.925) 

0.698 

(0.429-0.791) 

0.573 

(0.295-0.668) 0.295 1.127 

> 20.0 Mev 1.606 

(0.797-2.016) 

1.673 

(0.740-2.154) 

1.543 

(0.632-2.264) 

n/a 

0.632 2.264 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.758 

(0.532-1.797) 

1.310 

(0.470-1.333) 

0.955 

(0.324-0.978) 

0.734 

(0.244-0.746) 0.244 1.797 

10 - 100 keV 0.947 

(0.567-1.734) 

0.753 

(0.473-1.299) 

0.546 

(0.342-0.938) 

0.425 

(0.269-0.723) 0.269 1.734 

0.1 - 2.0 Mev 0.490 

(0.361-0.683) 

0.338 

(0.254-0.494) 

0.274 

(0.200-0.408) 

0.193 

(0.146-0.280) 0.146 0.683 

2.0 - 20.0 Mev 0.912 

(0.683-1.049) 

0.775 

(0.494-0.851) 

0.659 

(0.408-0.725) 

0.541 

(0.280-0.612) 0.280 1.049 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 68 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Esophagus 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.328E-09 

(2.50E-10 - 1.55E-9) 

1.681E-09 

(4.75E-10 - 1.90E-9) 

1.010E-09 

(2.65E-10 - 1.16E-9) 

7.175E-10 

(2.00E-10 - 8.35E-10) 2.00E-10 1.90E-09 

10 - 100 keV 3.045E-09 

(1.55E-9 - 4.22E-9) 

3.742E-09 

(1.90E-9 - 5.21E-9) 

2.371E-09 

(1.16E-9 - 3.26E-9) 

1.683E-09 

(8.35E-10 - 2.39E-9) 8.35E-10 5.21E-09 

0.1 - 2.0 Mev 1.612E-08 

(4.22E-9 - 2.77E-8) 

1.661E-08 

(5.21E-9 - 2.46E-8) 

1.068E-08 

(3.26E-9 - 1.82E-8) 

7.644E-09 

(2.39E-9 - 1.32E-8) 2.39E-09 2.77E-08 

2.0 - 20.0 Mev 4.303E-08 

(2.77E-8 - 4.52E-8) 

4.062E-08 

(2.46E-8 - 4.48E-8) 

3.679E-08 

(1.82E-8 - 4.08E-8) 

2.863E-08 

(1.32E-8 - 3.32E-8) 1.32E-08 4.52E-08 

> 20.0 Mev 4.874E-08 

(4.18E-8 - 5.96E-8) 

4.707E-08 

(4.37E-8 - 5.31E-8) 

4.712E-08 

(4.08E-8 - 5.61E-8) 

n/a 

4.08E-08 5.96E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.575 

(0.379-1.656) 

1.996 

(0.613-2.075) 

1.201 

(0.356-1.250) 

0.851 

(0.264-0.886) 0.264 2.075 

10 - 100 keV 0.787 

(0.479-1.476) 

0.949 

(0.592-1.814) 

0.585 

(0.370-1.109) 

0.425 

(0.272-0.795) 0.272 1.814 

0.1 - 2.0 Mev 0.427 

(0.277-0.661) 

0.445 

(0.349-0.592) 

0.283 

(0.197-0.434) 

0.204 

(0.154-0.313) 0.154 0.661 

2.0 - 20.0 Mev 0.919 

(0.661-1.101) 

0.859 

(0.586-0.986) 

0.785 

(0.434-0.910) 

0.601 

(0.313-0.670) 0.313 1.101 

> 20.0 Mev 1.634 

(0.718-2.385) 

1.560 

(0.746-2.122) 

1.572 

(0.679-2.243) 

n/a 

0.679 2.385 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.378 

(0.305-1.415) 

1.746 

(0.567-1.786) 

1.047 

(0.321-1.069) 

0.750 

(0.241-0.757) 0.241 1.786 

10 - 100 keV 0.775 

(0.466-1.384) 

0.937 

(0.575-1.700) 

0.591 

(0.359-1.039) 

0.421 

(0.264-0.746) 0.264 1.700 

0.1 - 2.0 Mev 0.412 

(0.267-0.628) 

0.430 

(0.336-0.575) 

0.271 

(0.190-0.412) 

0.196 

(0.148-0.298) 0.148 0.628 

2.0 - 20.0 Mev 0.869 

(0.628-1.037) 

0.812 

(0.557-0.907) 

0.735 

(0.412-0.837) 

0.569 

(0.298-0.619) 0.298 1.037 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 69 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Lung 

Nuetrons Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.283E-09 

(3.85E-10 - 1.46E-9) 

1.381E-09 

(4.05E-10 - 1.58E-9) 

9.128E-10 

(2.90E-10 - 1.04E-9) 

6.722E-10 

(2.35E-10 - 7.72E-10) 2.35E-10 1.58E-09 

10 - 100 keV 2.943E-09 

(1.46E-9 - 4.20E-9) 

3.349E-09 

(1.58E-9 - 4.81E-9) 

2.172E-09 

(1.04E-9 - 3.19E-9) 

1.650E-09 

(7.72E-10 - 2.42E-9) 7.72E-10 4.81E-09 

0.1 - 2.0 Mev 2.218E-08 

(4.20E-9 - 3.42E-8) 

2.669E-08 

(4.81E-9 - 4.09E-8) 

1.648E-08 

(3.19E-9 - 2.60E-8) 

1.196E-08 

(2.42E-9 - 1.99E-8) 2.42E-09 4.09E-08 

2.0 - 20.0 Mev 4.709E-08 

(3.42E-8 - 4.87E-8) 

5.132E-08 

(4.09E-8 - 5.26E-8) 

3.974E-08 

(2.60E-8 - 4.20E-8) 

3.282E-08 

(1.99E-8 - 3.63E-8) 1.99E-08 5.26E-08 

> 20.0 Mev 4.563E-08 

(4.54E-8 - 4.77E-8) 

4.487E-08 

(4.32E-8 - 5.06E-8) 

4.474E-08 

(4.18E-8 - 4.91E-8) 

n/a 

4.18E-08 5.06E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.523 

(0.524-1.587) 

1.646 

(0.583-1.711) 

1.070 

(0.400-1.120) 

0.795 

(0.297-0.824) 0.297 1.711 

10 - 100 keV 0.751 

(0.478-1.392) 

0.820 

(0.547-1.506) 

0.541 

(0.363-0.994) 

0.410 

(0.275-0.735) 0.275 1.506 

0.1 - 2.0 Mev 0.579 

(0.405-0.813) 

0.699 

(0.496-0.974) 

0.429 

(0.296-0.619) 

0.310 

(0.203-0.475) 0.203 0.974 

2.0 - 20.0 Mev 1.004 

(0.794-1.183) 

1.097 

(0.844-1.310) 

0.845 

(0.619-0.984) 

0.694 

(0.475-0.787) 0.475 1.310 

> 20.0 Mev 1.492 

(0.794-1.858) 

1.453 

(0.844-1.771) 

1.481 

(0.700-1.963) 

n/a 

0.700 1.963 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.332 

(0.470-1.358) 

1.436 

(0.495-1.462) 

0.847 

(0.354-0.966) 

0.697 

(0.276-0.708) 0.276 1.462 

10 - 100 keV 0.737 

(0.464-1.305) 

0.802 

(0.531-1.412) 

0.533 

(0.352-0.932) 

0.406 

(0.267-0.689) 0.267 1.412 

0.1 - 2.0 Mev 0.557 

(0.383-0.773) 

0.671 

(0.470-0.926) 

0.414 

(0.280-0.588) 

0.300 

(0.192-0.451) 0.192 0.926 

2.0 - 20.0 Mev 0.950 

(0.773-1.115) 

1.040 

(0.844-1.238) 

0.798 

(0.588-0.916) 

0.656 

(0.451-0.738) 0.451 1.238 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 70 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Gonads (female - ovaries) 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.610E-09 

(3.75E-10 - 1.86E-9) 

1.492E-09 

(4.00E-10 - 1.71E-9) 

9.845E-10 

(2.50E-10 - 1.13E-9) 

6.959E-10 

(1.90E-10 - 8.10E-10) 1.90E-10 1.86E-09 

10 - 100 keV 3.702E-09 

(1.86E-9 - 5.08E-9) 

3.224E-09 

(1.71E-9 - 4.97E-9) 

2.425E-09 

(1.13E-9 - 3.43E-9) 

1.756E-09 

(8.10E-10 - 2.49E-9) 8.10E-10 5.08E-09 

0.1 - 2.0 Mev 1.659E-08 

(5.08E-9 - 2.69E-8) 

1.755E-08 

(4.97E-9 - 2.72E-8) 

1.026E-08 

(3.43E-9 - 1.87E-8) 

6.955E-09 

(2.49E-9 - 1.18E-8) 2.49E-09 2.72E-08 

2.0 - 20.0 Mev 4.500E-08 

(2.69E-8 - 4.79E-8) 

4.564E-08 

(2.72E-8 - 5.07E-8) 

3.594E-08 

(1.87E-8 - 3.97E-8) 

2.873E-08 

(1.18E-8 - 3.27E-8) 1.18E-08 5.07E-08 

> 20.0 Mev 5.053E-08 

(4.55E-8 - 5.96E-8) 

4.746E-08 

(4.65E-8 - 5.07E-8) 

5.011E-08 

(3.97E-8 - 5.71E-8) 

n/a 

3.97E-08 5.96E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.910 

(0.556-1.999) 

1.775 

(0.528-1.841) 

1.168 

(0.379-1.209) 

0.825 

(0.239-0.859) 0.239 1.999 

10 - 100 keV 0.950 

(0.578-1.771) 

0.886 

(0.565-1.627) 

0.606 

(0.390-1.072) 

0.440 

(0.283-0.771) 0.283 1.771 

0.1 - 2.0 Mev 0.439 

(0.310-0.640) 

0.437 

(0.321-0.648) 

0.277 

(0.189-0.446) 

0.187 

(0.143-0.283) 0.143 0.648 

2.0 - 20.0 Mev 0.955 

(0.640-1.127) 

0.966 

(0.648-1.115) 

0.758 

(0.446-0.887) 

0.605 

(0.280-0.707) 0.280 1.127 

> 20.0 Mev 1.684 

(0.784-2.385) 

1.549 

(0.845-1.902) 

1.677 

(0.661-2.284) 

n/a 

0.661 2.385 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.670 

(0.458-1.709) 

1.549 

(0.476-1.574) 

1.020 

(0.305-1.036) 

0.727 

(0.216-0.734) 0.216 1.709 

10 - 100 keV 0.935 

(0.561-1.661) 

0.875 

(0.549-1.525) 

0.599 

(0.379-1.005) 

0.436 

(0.274-0.723) 0.274 1.661 

0.1 - 2.0 Mev 0.424 

(0.298-0.608) 

0.423 

(0.309-0.616) 

0.265 

(0.184-0.424) 

0.181 

(0.138-0.274) 0.138 0.616 

2.0 - 20.0 Mev 0.903 

(0.608-1.042) 

0.913 

(0.616-1.040) 

0.717 

(0.424-0.820) 

0.571 

(0.266-0.649) 0.266 1.042 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 71 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Gonads (male - testes) 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.964E-09 

(1.00E-9 - 2.33E-9) 

6.421E-10 

(1.80E-10 - 7.28E-10) 

7.823E-10 

(3.40E-10 - 9.17E-10) 

6.032E-10 

(3.25E-10 - 7.09E-10) 1.80E-10 2.33E-09 

10 - 100 keV 6.309E-09 

(2.33E-9 - 1.04E-8) 

1.448E-09 

(7.28E-10 - 2.00E-9) 

2.300E-09 

(9.17E-10 - 3.61E-9) 

1.932E-09 

(7.09E-10 - 3.16E-9) 7.09E-10 1.04E-08 

0.1 - 2.0 Mev 5.070E-08 

(1.04E-8 - 6.36E-8) 

6.101E-09 

(2.00E-9 - 1.12E-8) 

1.845E-08 

(3.61E-9 - 2.65E-8) 

1.739E-08 

(3.16E-9 - 2.45E-8) 2.00E-09 6.36E-08 

2.0 - 20.0 Mev 6.001E-08 

(5.43E-8 - 6.39E-8) 

3.333E-08 

(1.12E-8 - 4.06E-8) 

3.626E-08 

(2.65E-8 - 3.90E-8) 

3.320E-08 

(2.45E-8 - 3.71E-8) 1.12E-08 6.39E-08 

> 20.0 Mev 3.278E-08 

(2.78E-8 - 5.43E-8) 

5.090E-08 

(4.06E-8 - 6.42E-8) 

4.318E-08 

(3.79E-8 - 5.15E-8) 

n/a 

2.78E-08 6.42E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 2.311 

(1.283-2.411) 

0.757 

(0.259-0.790) 

0.915 

(0.458-0.955) 

0.711 

(0.382-0.735) 0.259 2.411 

10 - 100 keV 1.478 

(1.181-2.223) 

0.373 

(0.228-0.693) 

0.556 

(0.410-0.874) 

0.450 

(0.359-0.675) 0.228 2.223 

0.1 - 2.0 Mev 1.349 

(1.147-1.515) 

0.163 

(0.113-0.265) 

0.483 

(0.378-0.632) 

0.456 

(0.348-0.582) 0.113 1.515 

2.0 - 20.0 Mev 1.293 

(0.906-1.550) 

0.695 

(0.265-0.791) 

0.772 

(0.632-0.884) 

0.702 

(0.582-0.777) 0.265 1.550 

> 20.0 Mev 1.030 

(0.906-1.135) 

1.718 

(0.677-2.567) 

1.442 

(0.650-2.062) 

n/a 

0.650 2.567 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 2.034 

(1.206-2.084) 

0.666 

(0.220-0.679) 

0.808 

(0.415-0.819) 

0.624 

(0.355-0.633) 0.220 2.084 

10 - 100 keV 1.466 

(1.147-2.084) 

0.363 

(0.221-0.650) 

0.550 

(0.398-0.819) 

0.448 

(0.349-0.633) 0.221 2.084 

0.1 - 2.0 Mev 1.307 

(1.089-1.440) 

0.152 

(0.110-0.252) 

0.470 

(0.357-0.600) 

0.440 

(0.330-0.553) 0.110 1.440 

2.0 - 20.0 Mev 1.222 

(0.906-1.490) 

0.658 

(0.252-0.721) 

0.729 

(0.600-0.825) 

0.664 

(0.553-0.723) 0.252 1.490 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 72 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Liver 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.715E-09 

(4.90E-10 - 1.95E-9) 

1.294E-09 

(3.50E-10 - 1.48E-9) 

1.079E-09 

(3.05E-10 - 1.24E-9) 

7.280E-10 

(2.30E-10 - 8.35E-10) 2.30E-10 1.95E-09 

10 - 100 keV 3.960E-09 

(1.95E-9 - 5.63E-9) 

2.869E-09 

(1.48E-9 - 4.23E-9) 

2.511E-09 

(1.24E-9 - 3.59E-9) 

1.826E-09 

(8.35E-10 - 2.63E-9) 8.35E-10 5.63E-09 

0.1 - 2.0 Mev 2.520E-08 

(5.63E-9 - 3.71E-8) 

1.617E-08 

(4.23E-9 - 2.55E-8) 

1.509E-08 

(3.59E-9 - 2.36E-8) 

1.008E-08 

(2.63E-9 - 1.70E-8) 2.63E-09 3.71E-08 

2.0 - 20.0 Mev 4.904E-08 

(3.71E-8 - 5.09E-8) 

4.108E-08 

(2.55E-8 - 4.42E-8) 

3.797E-08 

(2.36E-8 - 4.08E-8) 

3.059E-08 

(1.70E-8 - 3.44E-8) 1.70E-08 5.09E-08 

> 20.0 Mev 4.413E-08 

(4.31E-8 - 4.89E-8) 

4.623E-08 

(4.29E-8 - 5.20E-8) 

4.569E-08 

(4.08E-8 - 4.92E-8) 

n/a 

4.08E-08 5.20E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 2.038 

(0.667-2.116) 

1.536 

(0.511-1.594) 

1.275 

(0.394-1.333) 

0.860 

(0.311-0.893) 0.311 2.116 

10 - 100 keV 0.997 

(0.640-1.856) 

0.753 

(0.481-1.410) 

0.631 

(0.408-1.181) 

0.452 

(0.299-0.795) 0.299 1.856 

0.1 - 2.0 Mev 0.664 

(0.508-0.884) 

0.421 

(0.314-0.607) 

0.391 

(0.291-0.562) 

0.268 

(0.182-0.404) 0.182 0.884 

2.0 - 20.0 Mev 1.047 

(0.816-1.231) 

0.873 

(0.607-1.008) 

0.806 

(0.562-0.941) 

0.644 

(0.404-0.723) 0.404 1.231 

> 20.0 Mev 1.442 

(0.816-1.809) 

1.532 

(0.735-2.082) 

1.516 

(0.680-1.970) 

n/a 

0.680 2.082 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.778 

(0.598-1.815) 

1.349 

(0.427-1.370) 

1.121 

(0.356-1.139) 

0.754 

(0.281-0.767) 0.281 1.815 

10 - 100 keV 0.983 

(0.621-1.740) 

0.743 

(0.467-1.322) 

0.623 

(0.397-1.107) 

0.447 

(0.290-0.746) 0.290 1.740 

0.1 - 2.0 Mev 0.641 

(0.481-0.840) 

0.407 

(0.301-0.577) 

0.381 

(0.276-0.534) 

0.259 

(0.175-0.384) 0.175 0.840 

2.0 - 20.0 Mev 0.990 

(0.816-1.157) 

0.825 

(0.577-0.935) 

0.761 

(0.534-0.870) 

0.609 

(0.384-0.669) 0.384 1.157 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 73 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Remainder Organs 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.285E-09 

(4.00E-10 - 1.50E-9) 

1.345E-09 

(4.25E-10 - 1.57E-9) 

9.441E-10 

(2.85E-10 - 1.10E-9) 

6.383E-10 

(2.20E-10 - 7.47E-10) 2.20E-10 1.57E-09 

10 - 100 keV 3.355E-09 

(1.50E-9 - 4.97E-9) 

3.799E-09 

(1.57E-9 - 5.58E-9) 

2.414E-09 

(1.10E-9 - 3.53E-9) 

1.911E-09 

(7.47E-10 - 2.76E-9) 7.47E-10 5.58E-09 

0.1 - 2.0 Mev 2.057E-08 

(4.97E-9 - 3.09E-8) 

2.272E-08 

(5.58E-9 - 3.40E-8) 

1.622E-08 

(3.53E-9 - 2.53E-8) 

1.189E-08 

(2.76E-9 - 1.92E-8) 2.76E-09 3.40E-08 

2.0 - 20.0 Mev 4.422E-08 

(3.09E-8 - 4.64E-8) 

4.633E-08 

(3.40E-8 - 4.79E-8) 

3.875E-08 

(2.53E-8 - 4.10E-8) 

3.273E-08 

(1.92E-8 - 3.65E-8) 1.92E-08 4.79E-08 

> 20.0 Mev 4.906E-08 

(4.63E-8 - 5.20E-8) 

4.916E-08 

(4.61E-8 - 5.41E-8) 

4.797E-08 

(4.10E-8 - 5.61E-8) 

n/a 

4.10E-08 5.61E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.524 

(0.556-1.587) 

1.595 

(0.599-1.656) 

1.120 

(0.400-1.168) 

0.756 

(0.316-0.783) 0.316 1.656 

10 - 100 keV 0.830 

(0.565-1.428) 

0.905 

(0.634-1.494) 

0.600 

(0.401-1.048) 

0.439 

(0.314-0.711) 0.314 1.494 

0.1 - 2.0 Mev 0.540 

(0.426-0.735) 

0.595 

(0.470-0.809) 

0.422 

(0.309-0.603) 

0.314 

(0.241-0.458) 0.241 0.809 

2.0 - 20.0 Mev 0.942 

(0.735-1.096) 

0.990 

(0.785-1.157) 

0.824 

(0.603-0.960) 

0.692 

(0.458-0.784) 0.458 1.157 

> 20.0 Mev 1.620 

(0.773-2.092) 

1.627 

(0.785-2.163) 

1.604 

(0.684-2.243) 

n/a 

0.684 2.243 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.331 

(0.488-1.356) 

1.397 

(0.519-1.415) 

0.982 

(0.348-0.998) 

0.666 

(0.269-0.669) 0.269 1.415 

10 - 100 keV 0.819 

(0.549-1.339) 

0.895 

(0.616-1.401) 

0.592 

(0.389-0.983) 

0.435 

(0.305-0.667) 0.305 1.401 

0.1 - 2.0 Mev 0.525 

(0.407-0.698) 

0.577 

(0.452-0.769) 

0.409 

(0.292-0.573) 

0.301 

(0.230-0.435) 0.230 0.769 

2.0 - 20.0 Mev 0.889 

(0.698-1.021) 

0.934 

(0.769-1.094) 

0.778 

(0.573-0.892) 

0.655 

(0.435-0.733) 0.435 1.094 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 74 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Skin 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 9.326E-10 

(6.75E-10 - 1.23E-9) 

9.267E-10 

(6.50E-10 - 1.22E-9) 

7.056E-10 

(5.00E-10 - 9.49E-10) 

5.190E-10 

(3.95E-10 - 6.96E-10) 3.95E-10 1.23E-09 

10 - 100 keV 4.398E-09 

(1.23E-9 - 7.57E-9) 

4.382E-09 

(1.22E-9 - 7.54E-9) 

3.671E-09 

(9.49E-10 - 6.40E-9) 

3.376E-09 

(6.96E-10 - 6.00E-9) 6.96E-10 7.57E-09 

0.1 - 2.0 Mev 3.294E-08 

(7.57E-9 - 4.14E-8) 

3.282E-08 

(7.54E-9 - 4.14E-8) 

3.012E-08 

(6.40E-9 - 3.85E-8) 

2.776E-08 

(6.00E-9 - 3.59E-8) 6.00E-09 4.14E-08 

2.0 - 20.0 Mev 4.545E-08 

(4.14E-8 - 4.75E-8) 

4.543E-08 

(4.14E-8 - 4.75E-8) 

4.270E-08 

(3.85E-8 - 4.43E-8) 

3.936E-08 

(3.59E-8 - 4.09E-8) 3.59E-08 4.75E-08 

> 20.0 Mev 2.985E-08 

(2.67E-8 - 4.33E-8) 

2.977E-08 

(2.66E-8 - 4.33E-8) 

3.023E-08 

(2.75E-8 - 4.11E-8) 

n/a 

2.66E-08 4.33E-08 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.091 

(0.596-1.169) 

1.086 

(0.585-1.163) 

0.830 

(0.441-0.904) 

0.610 

(0.322-0.663) 0.322 1.169 

10 - 100 keV 0.989 

(0.860-1.169) 

0.986 

(0.857-1.163) 

0.816 

(0.727-0.913) 

0.714 

(0.663-0.753) 0.663 1.169 

0.1 - 2.0 Mev 0.879 

(0.817-0.987) 

0.876 

(0.815-0.987) 

0.801 

(0.710-0.917) 

0.738 

(0.661-0.855) 0.661 0.987 

2.0 - 20.0 Mev 0.982 

(0.722-1.127) 

0.981 

(0.722-1.127) 

0.925 

(0.685-1.067) 

0.840 

(0.665-0.966) 0.665 1.127 

> 20.0 Mev 0.961 

(0.722-1.328) 

0.958 

(0.722-1.330) 

0.980 

(0.674-1.370) 

n/a 

0.674 1.370 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 0.955 

(0.592-1.096) 

0.957 

(0.585-1.090) 

0.729 

(0.437-0.847) 

0.538 

(0.313-0.621) 0.313 1.096 

10 - 100 keV 0.986 

(0.836-1.117) 

0.982 

(0.832-1.117) 

0.814 

(0.706-0.887) 

0.714 

(0.621-0.765) 0.621 1.117 

0.1 - 2.0 Mev 0.853 

(0.773-0.938) 

0.850 

(0.770-0.938) 

0.776 

(0.674-0.871) 

0.713 

(0.625-0.812) 0.625 0.938 

2.0 - 20.0 Mev 0.918 

(0.722-1.052) 

0.917 

(0.722-1.050) 

0.863 

(0.685-1.003) 

0.794 

(0.665-0.922) 0.665 1.052 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 75 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Stomach 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 2.162E-09 

(6.15E-10 - 2.45E-9) 

9.786E-10 

(2.50E-10 - 1.12E-9) 

9.915E-10 

(2.95E-10 - 1.13E-9) 

7.128E-10 

(2.25E-10 - 8.16E-10) 2.25E-10 2.45E-09 

10 - 100 keV 4.904E-09 

(2.45E-9 - 6.93E-9) 

2.302E-09 

(1.12E-9 - 3.18E-9) 

2.401E-09 

(1.13E-9 - 3.42E-9) 

1.771E-09 

(8.16E-10 - 2.58E-9) 8.16E-10 6.93E-09 

0.1 - 2.0 Mev 3.238E-08 

(6.93E-9 - 4.58E-8) 

8.968E-09 

(3.18E-9 - 1.53E-8) 

1.387E-08 

(3.42E-9 - 2.13E-8) 

1.008E-08 

(2.58E-9 - 1.63E-8) 2.58E-09 4.58E-08 

2.0 - 20.0 Mev 5.432E-08 

(4.58E-8 - 5.58E-8) 

3.416E-08 

(1.53E-8 - 3.96E-8) 

3.537E-08 

(2.13E-8 - 3.95E-8) 

2.935E-08 

(1.63E-8 - 3.35E-8) 1.53E-08 5.58E-08 

> 20.0 Mev 4.531E-08 

(4.09E-8 - 5.30E-8) 

5.196E-08 

(3.96E-8 - 6.32E-8) 

4.673E-08 

(3.95E-8 - 5.81E-8) 

n/a 

3.95E-08 6.32E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 2.567 

(0.889-2.679) 

1.161 

(0.356-1.209) 

1.176 

(0.406-1.216) 

0.844 

(0.316-0.872) 0.316 2.679 

10 - 100 keV 1.244 

(0.787-2.332) 

0.579 

(0.361-1.066) 

0.593 

(0.388-1.079) 

0.441 

(0.293-0.777) 0.293 2.332 

0.1 - 2.0 Mev 0.858 

(0.675-1.090) 

0.236 

(0.171-0.364) 

0.365 

(0.277-0.508) 

0.266 

(0.192-0.388) 0.171 1.090 

2.0 - 20.0 Mev 1.160 

(0.883-1.387) 

0.721 

(0.364-0.830) 

0.748 

(0.508-0.849) 

0.618 

(0.388-0.694) 0.364 1.387 

> 20.0 Mev 1.458 

(0.883-1.726) 

1.752 

(0.660-2.526) 

1.570 

(0.659-2.324) 

n/a 

0.659 2.526 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 2.244 

(0.751-2.295) 

1.016 

(0.305-1.033) 

1.028 

(0.360-1.042) 

0.738 

(0.275-0.750) 0.275 2.295 

10 - 100 keV 1.221 

(0.765-2.186) 

0.571 

(0.351-1.000) 

0.584 

(0.377-1.011) 

0.437 

(0.285-0.729) 0.285 2.186 

0.1 - 2.0 Mev 0.824 

(0.639-1.036) 

0.226 

(0.166-0.351) 

0.351 

(0.263-0.483) 

0.256 

(0.185-0.369) 0.166 1.036 

2.0 - 20.0 Mev 1.099 

(0.883-1.312) 

0.682 

(0.346-0.760) 

0.707 

(0.483-0.782) 

0.584 

(0.369-0.641) 0.346 1.312 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 76 of 77 

November 21, 2007 3 OCAS-IG-001 

Organ: Thyroid 

Neutron Exposures 

Fluence (φ) to Organ Dose Equivalent (HT) (cSv cm2

) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.526E-09 

(7.05E-10 - 1.80E-9) 

5.344E-10 

(1.45E-10 - 6.07E-10) 

8.223E-10 

(3.70E-10 - 9.62E-10) 

5.675E-10 

(2.95E-10 - 6.58E-10) 1.45E-10 1.80E-09 

10 - 100 keV 4.581E-09 

(1.80E-9 - 7.51E-9) 

1.037E-09 

(6.07E-10 - 1.62E-9) 

2.402E-09 

(9.62E-10 - 3.77E-9) 

1.707E-09 

(6.58E-10 - 2.55E-9) 6.07E-10 7.51E-09 

0.1 - 2.0 Mev 4.256E-08 

(7.51E-9 - 5.57E-8) 

5.291E-09 

(1.62E-9 - 9.83E-9) 

2.195E-08 

(3.77E-9 - 3.24E-8) 

1.219E-08 

(2.55E-9 - 1.82E-8) 1.62E-09 5.57E-08 

2.0 - 20.0 Mev 5.520E-08 

(5.18E-8 - 5.72E-8) 

2.543E-08 

(9.83E-9 - 3.14E-8) 

4.384E-08 

(3.24E-8 - 4.59E-8) 

3.257E-08 

(1.82E-8 - 4.07E-8) 9.83E-09 5.72E-08 

> 20.0 Mev 3.787E-08 

(3.18E-8 - 5.18E-8) 

5.471E-08 

(3.14E-8 - 6.72E-8) 

4.625E-08 

(4.56E-8 - 4.66E-8) 

n/a 

3.14E-08 6.72E-08 

Ambient Dose Equivalent (H*(10)) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.803 

(0.919-1.882) 

0.623 

(0.193-0.660) 

0.964 

(0.425-1.010) 

0.674 

(0.298-0.694) 0.193 1.882 

10 - 100 keV 1.079 

(0.853-1.717) 

0.311 

(0.184-0.578) 

0.579 

(0.428-0.916) 

0.398 

(0.290-0.627) 0.184 1.717 

0.1 - 2.0 Mev 1.125 

(0.848-1.325) 

0.144 

(0.092-0.234) 

0.567 

(0.400-0.772) 

0.320 

(0.248-0.434) 0.092 1.325 

2.0 - 20.0 Mev 1.186 

(0.864-1.418) 

0.533 

(0.234-0.611) 

0.934 

(0.765-1.081) 

0.682 

(0.434-0.729) 0.234 1.418 

> 20.0 Mev 1.199 

(0.864-1.351) 

1.864 

(0.524-2.688) 

1.515 

(0.765-1.881) 

n/a 

0.524 2.688 

Deep Dose Equivalent Hp,slab(10) to Organ Dose Equivalent (HT) (cSv/cSv) 

Neutron Energy DCFAP DCFPA DCFROT DCFISO DCFMin DCFMax 

<10 keV 1.579 

(0.861-1.610) 

0.554 

(0.177-0.568) 

0.856 

(0.395-0.863) 

0.588 

(0.303-0.595) 0.177 1.610 

10 - 100 keV 1.066 

(0.829-1.610) 

0.302 

(0.179-0.542) 

0.571 

(0.416-0.859) 

0.391 

(0.281-0.587) 0.179 1.610 

0.1 - 2.0 Mev 1.086 

(0.805-1.259) 

0.132 

(0.089-0.222) 

0.552 

(0.378-0.734) 

0.309 

(0.235-0.412) 0.089 1.259 

2.0 - 20.0 Mev 1.123 

(0.864-1.355) 

0.504 

(0.222-0.561) 

0.881 

(0.734-1.013) 

0.644 

(0.412-0.692) 0.222 1.355 

> 20.0 Mev n/a n/a n/a n/a 

n/a n/a 
 

 

CLAIMANT CAN

 

CER DIAGNOSES 

Primary 

Cancer #1 

Primary 

Cancer #2 

 

Primary Cancer 

#3 

 

Secondary 

Cancer #1 

 

Secondary 

Cancer #2 

 

Secondary 

Cancer #3 

Cancer Type N/A N/A N/A N/A N/A N/A 

Date of 

Daignosis N/A N/A N/A N/A N/A N/A 

 

 

 

Effective Date: Revision No. OCAS Document No. Page 77 of 77 

November 21, 2007 3 OCAS-IG-001 

APPENDIX B - IREP-EXCEL INPUT FORMAT 

PERSONAL INFORMATION 

Claimant 

Name Claim # Claimant SSN 

DOL Claim 

Center Gender Birth Year Year of Diagnosis Cancer Model Should alt model be run? 

John Q. 

Doe 

000001-

DE 123-45-6789 Denver CO Male 1942 2002 

Oral Cavity 

and Pharynx No 

EXPOSURE 

INFORMATION 

Number of 

exposures 

1 

Exposure # Exposure 

Year 

Exposure 

Rate Radiation Type 

Dose 

Distribution 

Type 

Parameter 

1 

Parameter 

2 

Parameter 

3 

1 1982 chronic electrons Lognormal 2.000 2.000 0.000 

2 1982 chronic electrons Lognormal 2.000 2.000 0.000 

3 1982 chronic electrons Lognormal 2.000 2.000 0.000 

4 1982 chronic electrons Lognormal 2.000 2.000 0.000 

5 1982 chronic electrons Lognormal 2.000 2.000 0.000 

6 1982 chronic electrons Lognormal 2.000 2.000 0.000 

7 1982 chronic electrons Lognormal 2.000 2.000 0.000 

8 1982 chronic electrons Lognormal 2.000 2.000 0.000 

9 1982 chronic electrons Lognormal 2.000 2.000 0.000 

10 1982 chronic electrons Lognormal 2.000 2.000 0.000 

11 1982 chronic electrons Lognormal 2.000 2.000 0.000 

12 1982 chronic electrons Lognormal 2.000 2.000 0.000 

13 1982 chronic electrons Lognormal 2.000 2.000 0.000 

14 1982 chronic electrons Lognormal 2.000 2.000 0.000 

15 1982 chronic electrons Lognormal 2.000 2.000 0.000 

16 1982 chronic electrons Lognormal 2.000 2.000 0.000 

17 1982 chronic electrons Lognormal 2.000 2.000 0.000 

18 1982 chronic electrons Lognormal 2.000 2.000 0.000 

19 1982 chronic electrons Lognormal 2.000 2.000 0.000 

20 1982 chronic electrons Lognormal 2.000 2.000 0.000 

21 1982 chronic electrons Lognormal 2.000 2.000 0.000 

22 1982 chronic electrons Lognormal 2.000 2.000 0.000 

23 1982 chronic electrons Lognormal 2.000 2.000 0.000 

24 1982 chronic electrons Lognormal 2.000 2.000 0.000 

25 1982 chronic electrons Lognormal 2.000 2.000 0.000 

26 1982 chronic electrons Lognormal 2.000 2.000 0.000 

27 1982 chronic electrons Lognormal 2.000 2.000 0.000 

28 1982 chronic electrons Lognormal 2.000 2.000 0.000 

29 1982 chronic electrons Lognormal 2.000 2.000 0.000 

30 1982 chronic electrons Lognormal 2.000 2.000 0.000